Research & Development in France on Gen-IV Nuclear Energy Systems
|
|
- Douglas Potter
- 6 years ago
- Views:
Transcription
1 Research & Development in France on Gen-IV Nuclear Energy Systems Frank Carré François Gauché & Jacques Rouault CEA/ 1
2 R&D in France on Gen-IV Nuclear Energy Systems Contents 1 Status and mid-term plans for the deployment of LWRs and fuel cycle 2 National R&D plans on Fast Reactor prototype & advanced fuel cycles Sodium Fast Reactor & Protype ASTRID Gas Fast Reactor & Experimental Reactor ALLEGRO 3 Other Gen-IV Nuclear Energy Systems 4 Stakes in European & international cooperation 2
3 63 GWe PWR fleet & Spent fuel recycle for 25 years U nat Processing of U ore Mines Enrichment U dep U rep Pu Fuel fabrication Vitrified waste Waste Treatment of spent fuels Melox Retraitement du combustible usé et fabrication MOX ~1100t/yr La Hague Energy 58 PWRs ~63 GWe Paluel 3
4 Installed capacity (MWe) 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 ( ) Rate of construction : 2,000 MW/year Reactors PWRs (20 MOX) 63.2 GWe Existing fleet 40-year plant life EPR Foak Plant life extension beyond 40 years Generation 3+ Generation 4 0 Average plant life : 48 Source years : EDF ENC
5 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 Finland at Olkiluoto (TVO) in operation by 2012 July 05: French Energy Policy Act EPR of Flamanville-3 start in 2012 Jan 09: Decision on EPR as Penly-3 5
6 Generation III recycle of [UPu] with COEX The COEX plant New fuel (MOX) New fuel (MOX) PWR 2 nd /3 rd Gen Spent fuel COEX Treatment & Refabrication Spent fuel FBR 4 th Gen Co-management of [UPu] for recycle as MOX in Gen III/III+ or Gen IV reactors Waste package as vitrified FP & MA Standard canister for disposal SNF treatment and recycle best available technologies Enhanced resistance to proliferation (co-management of [UPu]) 6
7 A sustainable management of nuclear material & waste - The Act of June 28, 2006 National Plan for managing nuclear materials and radioactive waste Guarantees for long term funding of radioactive waste management Stepwise program for Long-Lived Waste (High and Medium Activity) management along various approaches: Partitioning & Transmutation: 2012: Assessment of Fast Reactors / ADS 2020: Fast reactor Prototype Retrievable Geological Repository: 2015: Authorization decree 2025: Beginning of operation Interim storage: Creation of new facilities in 2015 Atalante & Phenix 7
8 French Atomic Energy Commission Orientations (December 2006, confirmed May 2008) Two fast neutron systems studied in parallel A Sodium Fast Reactor as reference with the prototype ASTRID in the 2020s The most mature option but innovations sought to achieve progress and relevance to GEN IV systems In close connection with French industrial partners EDF and AREVA As a longer term option the Gas Fast Reactor with ALLEGRO as the first experimental GFR European collaboration sought for hosting ALLEGRO in Europe 8
9 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 " 9
10 Time line of ASTRID and associated facilities R&D Choice of ASTRID power End of Pre- Conceptual Design Decision to continue End of Conceptual Design Decision to build Public debate On Waste Storage (28 june, 2006 Act) Detailed Design Safety Report Construction Feasibility Report on minor actinides partitioning Position Report on minor actinides partitioning and transmutation Start-up of core manufacturing workshop (AFC) Start-up of MA bearing fuels fabrication facility (ALFA) 10
11 SFR Core designed for enhanced safety Ti lot CE Ti Nb V TS Ti bas C Ti Nb DS bas Ti Ti N9 T C MA Ti Nb DS4 MA V/V % CEA Ref. Alternative Ferritic steel 14 18%Cr Nanostructured ODS Martensitic steel 9%Cr Nanostructured ODS 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 design for subassembly (%) Swelling of austenitic Phénix claddings compare to F/M materials Average 316 Ti Average 15/15Ti Best lot of 15/15Ti Embrittlement limit Ferritic -martensitic (F/M) steel s, ODS included dose (dpa) Supernova, Matrix 1 and Matrix: two experiments in Phenix. For the future CEA Fabricated ODS tube 11
12 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 CO 2 ) Practical exclusion of large energy release in case of severe accident Reduced sodium void reactivity effect + Enhanced Doppler effect (carbide fuel) EMP Loop design & conversion with Gas Turbine without intermediate system Sodium/helium IHX & Gas Stripper Impact on safety features Gas stripper IHX Na Brayton Gas conversion cycle 12
13 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 Heat Exchanger Steam Generator Control Rods Turbine Generator Electrical Power 17 Hot Plenum Condenser Primary Sodium (Hot) Core Pump Pump Heat Sink Cold Plenum Primary Sodium (Cold) Pump Secondary Sodium SFR PWR 13
14 ASTRID: preliminary design choices / open options * 600 MWe reactor With an intermediate sodium circuit Pool type primary circuit Preliminary strategy for severe accidents (recuperator ) Oxide fuel at least for starting core Transmutation capability Preliminary design** Open design features Energy conversion Primary circuit design Devices to eliminate severe accidents (third shutdown level) Corium recuperator technology SGs materials and technology Innovative technologies for Na fires detection and mastering Fuel handling * Purely illustrative overhead ** Choices to be validated by mid
15 MA recycle options in Fast-neutron reactors U Heterogeneous MA recycle CU Advanced Partitioning PUREX /COEX FP LWR FR U (Np) (U)Pu(Np) Am & Cm MA CU Grouped Separation FP T U Pu U Pu Np Am Cm Separation of Am only FP CU PUREX /COEX U (Np) (U)Pu(Np) Am FP + Cm Dedicated fuels & targets with high MA content (10-15%) 15
16 Global Actinide Management in LWRs & Fast Reactors Minimizing waste with advanced actinide recycling Plutonium is the major contributor to the long term radiotoxicity of spent fuel Plutonium has a high energetic potential Plutonium recycling Radiotoxicity after 1000 years Relative radio toxicity MA + FP Plutonium recycling Pu + MA + FP Spent Fuel No reprocesisng Plutonium Uranium Ore (mine) FP P&T of MA Minor actinides (MA) Fission Products (FP) Time (years) After plutonium, MA have the major impact to the long term radiotoxicity MA transmutation 16
17 2020 Prototype Astrid & Fuel cycle facilities La Hague AFC (U,Pu)O 2 1 AFC : Core Manufacture Workshop 2 ALFA : Minor Actinides Fuel Fabrication Line in ATALANTE (Marcoule) ALFA (U,Pu,Np,Am,Cm)O 2 3 Core Assembly Workshop Minor Actinides Assembly Workshop ASTRID Prototype 3 5 Minor Actinide Fuel Analysis in ATALANTE 6 AFC Analysis Laboratory 17
18 GFR - Gas Fast reactor & Experimental Prototype Robust decay heat removal strategy (passive after 24hrs) 2007 Pre-feasibility report on 1 st reference concept 2012 Up-graded concept & Feasibility report GCFR EU-FP6 Project Snecma Fabrication Ceramic (SiC) clad fuel GFR 2400 MWt reference concept Allegro (75 MWt) 18
19 Allegro research reactor & GFR demonstrator Core 75 MW Fast Φ Dose Core volume Handling 30% Pu n/cm 2 /s 13 dpa/year 6 x 5 liters 8 d Experimental assembly Gas Fast Reactor Assembly Missions of Allegro: Test bed for GFR technology Innovative Fuel development Transmutation technology development Specific Heat processes loops Irradiation facility Fuel Control (CSD) Shutdown (DSD) Reflector Shield Fuel
20 GFR: key technologies development Ceramic clad carbide fuel: Improvement of ceramic composite cladding Development of a multilayer cladding Fuel element with a carbide actinide compound (pin, plate) Evaluation of a V alloy for cladding Severe accident phenomenology High temperature materials behavior 2012: demonstrate the fabricability of SiC cladding A technology breakthrough that opens new perspectives also for SFRs and LWRs Pre-conceptual studies on ALLEGRO 2012 Technical report on ALLEGRO for next steps 20
21 Nuclear H 2 & Heat for Transportation & Industry Primary Energy Electrolysis H 2 Thermochemical Cycle < 2008 BIOMASS + HYDROGEN C 6 H 9 O 4 + water 5.5 H2 BIOFUEL 6 -CH2- Transportation Distribution Storage 2 nd generation Biofuel Industrial applications Transportation (FC, ICE) 21
22 Generation IV International Forum (GIF) GIF Chairman Jacques Bouchard ( ) Yutaka Sagayama ( ) Chartered July 2001 Legal framework aimed at recognising each party s contribution China E.U. Russia Project Arrangements (technical cooperation agreements) VHTR GFR SFR SCWR LFR MSR 22
23 European Sustainable Nuclear Energy Technology Platform GEN II & III LWRs New materials & fuels Simulation & Experiments: reactor, safety, materials & fuels GEN IV (V)HTR Process heat, electricity & H 2 Energy Goals for Europe Security of Supply Competitiveness -20% GHG by 2020 Low carbon energy system by 2050 SET-Plan ( 07) R&D Infrastructures Safety rules GEN IV Fast Reactor &Closed Cycle (SFR, LFR, GFR, ADS) SNE-TP (Oct. 2007) R&D priority for industrial applications Needs for large experimental facilities Prototypes within the frame of Public/Private Partnerships European Industrial initiative 23
24 A CEA program on GEN IV systems consistent with the European Sustainable Nuclear Industrial Initiative 24
25 Education & Training Master in Nuclear Engineering Training Courses & Technical Visits Doctoral School 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) 25
26 R&D in France on Gen-IV Nuclear Energy Systems A French Vision of R&D Goals and Challenges LWRs and industrial experience of nuclear fuel recycle as stepping stone towards sustainable Fast Reactors with closed fuel cycles Perspectives on future nuclear reactors and fuel cycle framed by strategies of industrial partners (EDF, AREVA ) and the mandate of the Nuclear waste bill of 6/28, 2006 Prototype of Fast reactor by 2020 Demonstrations of recycling schemes promising for industrial application (Use of Uranium, Waste, Non-proliferation) Survey studies on nuclear cogeneration for H 2 and industrial process heat (processes, coupling, economics ) Federating national R&D programs into a consistent international technology roadmap (Gen IV, EU-SNE-TP ) Enhancing R&D and technology demonstrations, + Progressing towards harmonized international standards (safety, non-proliferation, physical protection ) 26
27 Back-up Slides 27
28 Hypotheses about the price of Uranium as a function of extracted amount Unat cost ($/kg) $/kg U nat Natural Uranium cost : patterns 21 st Edition of OECD/NEA Red Book : Uranium Resource, Production & Supply MtU <130 $/kg RAR EAR-I Total smooth threshold smooth-p Phosphates EAR-II SR Total MtUnat extracted Mt U nat extracted Source: CEA/DEN/I-TESE Study (2007) 28
29 Power conversion systems to minimize sodium risks 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 29
30 Enhanced in-service inspection & repair capabilities Need for improved In-Service Inspection (ISI) techniques for continuous monitoring and periodic inspection Need for efficient under sodium viewing and volumetric inspection capabilities: Experience acquired on Superphenix and Phenix Improvements needed (accuracy, range, volumetric NDT capability, robots) Focus on simplification of structures, for better accessibility and repair of component, primary system draining ISI&R of Phenix and SuperPhenix Work on further improvements to minimize investments risks 30
31 3-step strategy Partitioning of Minor Actinides: results & goals Demonstrations Spent Nuc Fuel PUREX U, Pu Np Sep. Am/Cm 2002 DIAMEX Nov SANEX Dec GANEX Fission products DIAMEX CO-EXTRACTION of An & Ln Ln SANEX Am & Cm SEPARATION of An from Ln Cm DIAMEX Am SÉPARATION of Am from Cm Nest steps: Am only, simplify DIAMEX-SANEX, demo GANEX 31
32 Generation IV International Forum New requirements to support a sustainable development Steady Progress: - Economic competitiveness - Safety and reliability Nuclear Power for centuries - Resource saving - HL Radwaste minimisation - Non-prolifération New applications Hydrogen, drinkable water, heat Industrial deployment ~2040 Multilateral cooperation with 3 levels of agreements: Intergovernmental Systems (x 6) R&D Projects (3 à 6 / System) China Charter: July 2001 Framework agreement: February 2005 E.U. Russia 32
Fast Neutron Reactors & Sustainable Development
International Conference on Fast Reactors and Related Fuel Cycles December 7th 11th, 2009, Kyoto, Japan Fast Neutron Reactors & Sustainable Development Jacques BOUCHARD Chairman of the Generation IV International
More informationNuclear Energy in France : Status, prospects and R&D strategy
International Workshop for Asian Nuclear Prospect Kobe, October 2008 Nuclear Energy in France : Status, prospects and R&D strategy Pierre-Yves CORDIER Nuclear Counsellor Embassy of France in Japan International
More informationIAEA/JAEA INTERNATIONAL WORKSHOP
IAEA/JAEA INTERNATIONAL WORKSHOP TOKAI-MURA, november 2007 NUCLEAR ENERGY IN THE 21th CENTURY: MAIN TRENDS AND POSSIBLE SCENARIOS IN FRANCE Bernard BOULLIS Program Director for fuel cycle technologies
More informationTHE FRENCH FAST REACTOR PROGRAM - INNOVATIONS IN SUPPORT TO HIGHER STANDARDS
INTERNATIONAL CONFERENCE ON FAST REACTORS AND RELATED FUEL CYCLES: SAFE TECHNOLOGIES AND SUSTAINABLE SCENARIOS (FR13) THE FRENCH FAST REACTOR PROGRAM - INNOVATIONS IN SUPPORT TO HIGHER STANDARDS François
More informationTHE FRENCH PROGRAM FOR A SUSTAINABLE MANAGEMENT OF NUCLEAR MATERIALS AND WASTE
THE FRENCH PROGRAM FOR A SUSTAINABLE MANAGEMENT OF NUCLEAR MATERIALS AND WASTE Bernard BOULLIS Fuel Cycle Back End Programs Director CEA, Nuclear Energy Division PAGE 1 International Symposium TOKYO, October
More informationConsiderations for a Sustainable Nuclear Fission Energy in Europe
International Conference Nuclear Energy for New Europe 2005 Bled Slovenia September 5-8 Considerations for a Sustainable Nuclear Fission Energy in Europe G. Cognet - P. Ledermann D.G. Cacuci CEA - France
More informationFuture nuclear systems: fuel cycle options and guidelines for research
OECD Nuclear Energy Agency 11th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation Future nuclear systems: fuel cycle options and guidelines for research Bernard
More informationTransmutation. Janne Wallenius Professor Reactor Physics, KTH. ACSEPT workshop, Lisbon
Transmutation Janne Wallenius Professor Reactor Physics, KTH Why would one want to transmute high level nuclear waste? Partitioning and transmutation of Pu, Am & Cm reduces the radio-toxic inventory of
More informationFRENCH R&D PROGRAM ON SFR AND THE ASTRID PROTOTYPE
FRENCH R&D PROGRAM ON SFR AND THE ASTRID PROTOTYPE FR13 Conference Christophe Béhar MARCH 4 th, 2012 CEA March 4th, 2012 French R&D program on SFR and the ASTRID prototype PAGE 1 WHY TO CHOOSE A FAST NEUTRON
More informationTECHNOLOGICAL BREAKTHROUGHS AND ELECTRICITY OF TOMORROW
TECHNOLOGICAL BREAKTHROUGHS AND ELECTRICITY OF TOMORROW Atoms for the future 2013 Christophe Béhar OCTOBER 21 st, 2013 Christophe Béhar October 21st, 2013 PAGE 1 THE ENERGY ISSUES Christophe Béhar October
More informationDesign features of Advanced Sodium Cooled Fast Reactors with Emphasis on Economics
FR09 7-11 December 2009 Kyoto, Japan Design features of Advanced Sodium Cooled Fast Reactors with Emphasis on Economics B. Riou AREVA NP D. Verwaerde EDF-R&D G. Mignot CEA Cadarache French SFR program
More informationOutlook on France s R&D Strategy on Future Nuclear Systems
Outlook on France s R&D Strategy on Future Nuclear Systems From Gen II to Gen IV reactors and fuel cycle Frank Carré, Claude Renault, Pascal Anzieu, Philippe Brossard and Pascal Yvon franck.carre@cea.fr
More informationFast Reactor Development in France
TSURUGA March 08, 2012 FBR Seminar Fast Reactor Development in France Jacques Bouchard 1 Fast Reactors : From the Beginning 1951 : the first fast neutron reactor and the first nuclear electricity production
More informationPlutonium Management in France. Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors
1 Plutonium Management in France Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors Christophe XERRI, Nuclear Counsellor 2 3 French Nuclear Fleet 2013 One operator:
More informationSeminar on Coolants for Fast Neutron Reactors. Frank Carré & Yves Bamberger CEA, Nuclear Energy Division, France
Seminar on Coolants for Fast Neutron Reactors Frank Carré & Yves Bamberger CEA, Nuclear Energy Division, France Maturity of Fast Reactor Types Sodium fast reactor ~400 reactor.year of operating experience
More informationLong term trends in nuclear production technologies. Noel Camarcat
Long term trends in nuclear production technologies Noel Camarcat Generation and Engineering Direction 1 EDF NUCLEAR FLEET IN FRANCE Nuclear electricity production plants Flamanville Brennilis 900 MW 1
More informationTHE ASTRID PROJECT STATUS, COLLABORATIONS, LESSONS FROM FUKUSHIMA ACCIDENT ADVANCED SODIUM TECHNOLOGICAL REACTOR FOR INDUSTRIAL DEMONSTRATION
ADVANCED SODIUM TECHNOLOGICAL REACTOR FOR INDUSTRIAL DEMONSTRATION THE ASTRID PROJECT STATUS, COLLABORATIONS, LESSONS FROM FUKUSHIMA ACCIDENT International Workshop on Prevention and Mitigation of Severe
More informationClosing the fuel cycle and Managing nuclear waste
Atomic Energy & Alternative Energies Commission CEA Closing the fuel cycle and Managing nuclear waste Walid BENZARTI walid.benzarti@gmail.com Closing the fuel cycle and managing nuclear waste July 6, 2010,
More informationFUTURE NUCLEAR FUEL CYCLES: GUIDELINES
ATOMS FOR FUTURE PARIS, 8-9 november, 2011 FUTURE NUCLEAR FUEL CYCLES: GUIDELINES Bernard BOULLIS, CEA, Nuclear Energy Division Program Director, Nuclear Fuel Cycle Back-end ATOMS FOR FUTURE PARIS, 8-9
More informationHarmonizing the French and American Policies for Nuclear Reactor Development
American Nuclear Society MIT Section Harmonizing the French and American Policies for Nuclear Reactor Development Frank Carré franck.carre@cea.fr Commissariat à l Energie Atomique 1 French, European &
More informationFrench R&D program on SFR and the
PRESENT STATUS OF FRENCH PROGRAM ASTRID JAPAN FRANCE COOPERATION EXPECTATIONS ON MONJU MONJU ASTRID ALAIN PORRACCHIA DIRECTOR FOR INNOVATION AND INDUSTRIAL SUPPORT CEA/DEN French R&D program on SFR and
More informationRECYCLING SPENT NUCLEAR FUELS FROM LWRS TO FAST REACTORS. Carole WAHIDE CEA Direction for Nuclear Energy FRANCE
RECYCLING SPENT NUCLEAR FUELS FROM LWRS TO FAST REACTORS Carole WAHIDE CEA Direction for Nuclear Energy FRANCE 1 FRENCH ELECTRICITY NUCLEAR > 75 % OF ELECTRICITY GENERATION LOW-CARBON ENERGY MIX : # 4G
More informationEII Team meeting Brussels, 13 September
European Strategic Nuclear Industrial Initiative Road Map and Concept Paper Noel Camarcat, Special Advisor for Nuclear R&D and International Issues, EDF Generation EII Team meeting Brussels, 13 September
More informationThe Legacy of U.S. Energy Leadership
Future Nuclear Energy Systems: Generation IV Kevan D. Weaver, Ph.D. U.S. System Integration Manager, Gas-Cooled Fast Reactor 50th Annual Meeting of the Health Physics Society 11 July 2005 - Spokane, Washington,
More informationRole of the Fast Reactor and Efforts on Monju
Int. Symposium on Present Status and Future Perspective for Reducing Radioactive Wastes ~ Aiming for Zero-Release~, Oct. 9-10, 2014, Tokyo Role of the Fast Reactor and Efforts on Monju October 9, 2014
More informationU.S. DOE currently has a number of initiatives to promote the growth of nuclear energy
U.S. Department of Energy Innovative Generation IV and Advanced Fuel Cycle Initiative Research Programs Buzz Savage AFCI Program Director U.S. DOE 1st COE-INES International Symposium Tokyo, Japan November
More informationR&D AT CEA FOR A SUSTAINABLE NUCLEAR ENERGY DEVELOPMENT
R&D AT CEA FOR A SUSTAINABLE NUCLEAR ENERGY DEVELOPMENT PIERRE-YVES CORDIER NUCLEAR ENERGY DIVISION CEA, FRANCE www.cea.fr OUTLINE The current situation France s example : more than 90% of electricity
More informationRadiochemistry Webinars
National Analytical Management Program (NAMP) U.S. Department of Energy Carlsbad Field Office Radiochemistry Webinars Nuclear Fuel Cycle Series Introduction to the Nuclear Fuel Cycle In Cooperation with
More informationSustainable Nuclear Energy technology Platform: SNETP. Deployment strategy: DS 2015
Sustainable Nuclear Energy technology Platform: SNETP Deployment strategy: DS 2015 Task force coordinated by Marylise Caron-Charles Status on July 8, 2015 NEA workshop on Nuclear Innovation roadmap 1 Purpose
More informationGeneration IV International Forum
Generation IV International Forum François Gauché GIF Policy Group Chairman International Workshop on advanced reactor systems and future energy market needs, 12 April 2017, OECD Conference Centre, Paris,
More informationThe Nuclear Fuel Cycle Simplified
The Nuclear Fuel Cycle Simplified Nuclear Power Committee August 27, 2009 Albert Machiels Senior Technical Executive Topics The Nuclear Fuel Cycle Simplified Light-Water Reactor (LWR) Power Block Used
More informationNext Generation Nuclear Reactors
Next Generation Nuclear Reactors Jacques BOUCHARD Commissariat à l Energie Atomique FRANCE WNU - Ottawa Jacques BOUCHARD, July 15, 2008 1 Session Contents - Introduction - Nuclear Reactor Generations ;
More informationFrench Strategy For GENIV reactors
French Strategy For GENIV reactors D. Verwaerde EDF/R&D with support of F. Gauché CEA-Nuclear Enery Division And J.F. Sauvage EDF/SEPTEN IAEA Technical Meeting - Vienne March 1st, 2012 Summary What needs
More informationGeneration IV Reactors
Generation IV Reactors Richard Stainsby National Nuclear Laboratory Recent Ex-Chair of the GFR System Steering Committee Euratom member of the SFR System Steering Committee What are Generation IV reactors?
More informationSaint-Petersburg Conference. Session 4. Drivers for Deployment of Sustainable and Innovative Technology
Saint-Petersburg Conference Session 4. Drivers for Deployment of Sustainable and Innovative Technology Speech by Christophe Behar, Director of the Nuclear Energy Division of the CEA Chairman, Ministers,
More informationConcept and technology status of HTR for industrial nuclear cogeneration
Concept and technology status of HTR for industrial nuclear cogeneration D. Hittner AREVA NP Process heat needs from industry Steam networks In situ heating HTR, GFR 800 C VHTR > 800 C MSR 600 C SFR, LFR,
More informationContribution of EURATOM in Fast Reactor R&D. Dr. Roland Schenkel. Director General Joint Research Centre European Commission
1 Contribution of EURATOM in Fast Reactor R&D Dr. Roland Schenkel Director General Joint Research Centre European Commission Outline of the presentation 2 Fast Reactor development in Europe: - the Sustainable
More informationFast and High Temperature Reactors for Improved Thermal Efficiency and Radioactive Waste Management
What s New in Power Reactor Technologies, Cogeneration and the Fuel Cycle Back End? A Side Event in the 58th General Conference, 24 Sept 2014 Fast and High Temperature Reactors for Improved Thermal Efficiency
More informationNEXT STEP FOR NUCLEAR POWER PLANT GENERATION IV
NEXT STEP FOR NUCLEAR POWER PLANT GENERATION IV Dr. Nicolas DEVICTOR CEA Nuclear energy division Program manager «Generation IV reactors» nicolas.devictor@cea.fr www.cea.fr JUNE, 27 2016 PAGE 1 PAGE 1
More informationGENERATION-IV SODIUM-COOLED FAST REACTORS AND THE ASTRID PROJECT
GENERATION-IV SODIUM-COOLED FAST REACTORS AND THE ASTRID PROJECT French-Swedish Seminar on Future Nuclear Systems Pascal Anzieu pascal.anzieu@cea.fr KTH, STOCKHOLM, DECEMBER 3, 2013 ESNII SNETP ESNII European
More informationEvolution of Nuclear Energy Systems
ALLEGRO Project 2 Evolution of Nuclear Energy Systems 3 General objectives Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types. Allegro Gas Fast Reactor (GFR)
More informationOVERVIEW OF CEA STUDIES ON FUTURE NUCLEAR ENERGY SYSTEMS
OVERVIEW OF CEA STUDIES ON FUTURE NUCLEAR ENERGY SYSTEMS Frank CARRE Future Nuclear Systems Project Manager 1 Overview of CEA studies on Future Nuclear Energy Systems Outline Advanced LWRs with improved
More informationThe European nuclear industry and research approach for innovation in nuclear energy. Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003
The European nuclear industry and research approach for innovation in nuclear energy Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003 Contents The EPS and MIT approach The approach of the European
More informationJAEA s Efforts for Reduction of Radioactive Wastes
International Symposium on Present Status and Future Perspective for Reducing of Radioactive Wastes JAEA s Efforts for Reduction of Radioactive Wastes February 17, 2016 Yasushi Taguchi Executive Vice President
More informationCurrent Status and Future Challenges of Innovative Reactors Development in Japan
Innovation for Cool Earth Forum 2017, Tokyo, Japan, October 4-5, 2017 Current Status and Future Challenges of Innovative Reactors Development in Japan 5 October, 2017 Yutaka Sagayama Assistant to the President
More informationGas-cooled Fast Reactor Status and program. Pascal ANZIEU Commissariat à l énergie atomique Atomic Energy Commission France
Gas-cooled Fast Reactor Status and program Pascal ANZIEU Commissariat à l énergie atomique Atomic Energy Commission France Nuclear Energy Division P. Anzieu - GFR Status 1 GFR: an alternative Fast Neutrons
More informationCurrent Status of the Gas Fast Reactor Demonstrator ALLEGRO
Current Status of the Gas Fast Reactor Demonstrator ALLEGRO ABSTRACT Ladislav Bělovský 1 ÚJV Řež, a.s. Husinec - Řež, Hlavní čp. 130, CZ 250 68, Czech Republic ladislav.belovsky@ujv.cz Jozef Molnár 1,
More informationThe Nuclear Fuel Cycle Lecture 5
The Nuclear Fuel Cycle Lecture 5 David J. Hamilton d.hamilton@physics.gla.ac.uk 7th February 2011 1. Overview Limitations of thermal recycling of Pu. Fast critical reactors: core physics; breeders; transmutation.
More informationFRENCH WASTE MANAGEMENT STRATEGY FOR A SUSTAINABLE DEVELOPMENT OF NUCLEAR ENERGY
FRENCH WASTE MANAGEMENT STRATEGY FOR A SUSTAINABLE DEVELOPMENT OF NUCLEAR ENERGY Charles Courtois and Franck Carré Waste Management Research Direction CEA/Saclay, Gif-sur-Yvette, Cedex, France Abstract
More informationTHE SODIUM-COOLED FAST REACTOR (SFR)
THE SODIUM-COOLED FAST REACTOR (SFR) M. J. Lineberry and T. R. Allen Argonne National Laboratory PO Box 2528 Idaho Falls, Id 83403-2528, U.S.A. 208-533-7760 todd.allen@anlw.anl.gov SUMMARY The Sodium-cooled
More informationWorkshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at
PR&PP Collaborative Study with GIF System Steering Committees A Compilation of Design Information and Crosscutting Issues Related to PR&PP Characterization Presented at Workshop on PR&PP Evaluation Methodology
More informationIMPACT OF A PROGRESSIVE DEPLOYMENT OF FAST REACTORS IN A PWR FLEET
IMPACT OF A PROGRESSIVE DEPLOYMENT OF FAST REACTORS IN A PWR FLEET Christine Chabert, Anne Saturnin CEA Cadarache, DEN/DER AIEA TECHNICAL MEETING, Advanced Fuel Cycles for Waste Burden Minimization June
More informationNuclear Energy in France Current Trends and Impact on the Bilateral Ties with Japan
1 Nuclear Energy in France Current Trends and Impact on the Bilateral Ties with Japan Dr Sunil Félix Nuclear Counsellor French Embassy in Tokyo Seminar on Nuclear Power Industry and WNE April 25, 2017
More informationModule 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria
Module 12 Generation IV Nuclear Power Plants Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Generation IV Participants Evolution of Nuclear
More informationOverview of GEN IV Demonstration Projects in China Jiashu, TIAN, EG Member China National Nuclear Corporation
Overview of GEN IV Demonstration Projects in China Jiashu, TIAN, EG Member China National Nuclear Corporation 4th GIF Symposium Presentation UIC, Paris, France October 16-17, 2018 Main Outlines VHTR -
More informationFROM RESEARCH TO INDUSTRY
FROM RESEARCH TO INDUSTRY INTERNATIONAL CONFERENCE ON FAST REACTORS AND RELATED FUEL CYCLES FRENCH STRATEGY AND PROGRAMS Bernard BIGOT - CEO CEA -Alternative Energies and Atomic Energy Commission Paris-
More informationClosed Fuel Cycle Strategies and National Programmes in Russia
Closed Fuel Cycle Strategies and National Programmes in Russia A.V. Bychkov RIAR, RUSSIA 9 th IEM on Actinide and Fission Products Partitioning and Transmutation Nimes, France, 25-29 September 2006 Unique
More informationSFR System Status and Plans
SFR System Status and Plans Dohee Hahn SFR SSC Chair GIF Symposium San Diego November 15-16, 2012 Outline Overview of SFR R&D Key Priority Objectives Project Status Application of GIF Methodologies Challenging
More informationDevelopment of FBR Fuel Cycle Technology in Japan
International Conference on Fast Reactors And Related Fuel Cycles: Development of FBR Fuel Cycle Technology in Japan December 8, 2009 H. FUNASAKA, T. KOYAMA, T. NAMEKAWA and T. NAGATA Advanced Nuclear
More informationUsed Nuclear Fuel Management Options
Used Nuclear Fuel Management Options Main challenges and AREVA overall positioning November 15, 2016 Isabelle Morlaes, AREVA, Sales Back-End Dpt. SVP France & New Business Development AREVA Proprietary
More informationMarket perspectives and challenges for GEN-4 systems
Market perspectives and challenges for GEN-4 systems Hideki Kamide Vice Chair, The Generation IV International Forum (GIF) Current status of Fukushima Daiichi Nuclear Power Station (NPS) Mid-and-Long-Term
More informationThe Nuclear Fuel Cycle Lecture 4
The Nuclear Fuel Cycle Lecture 4 David J. Hamilton d.hamilton@physics.gla.ac.uk 31st January 2011 1. Overview The back-end of the cycle (continued): Once-through and geological disposal; Reprocessing-recycling
More informationAdvanced and innovative reactor concept designs, associated objectives and driving forces
International Conference on Fast Reactors and Related Fuel Cycles (FR09) 7-11 December 2009, Kyoto, Japan Advanced and innovative reactor concept designs, associated objectives and driving forces Jean-Louis
More informationThe role of nuclear power in Janne Wallenius Professor Reactor Physics, KTH
The role of nuclear power in 2050 Janne Wallenius Professor Reactor Physics, KTH Questions to be addressed How efficient has nuclear power been in reducing CO2 emissions? To what extent can nuclear contribute
More informationEfforts for Next Generations Reactor Systems Development in the World
Efforts for Next Generations Reactor Systems Development in the World 1 Renewed interest in sustainable nuclear energy systems 2 Generation IV International Forum and IAEA INPRO Initiatives 3 R&D on Fast
More informationNear-term Options for Treatment and Recyle
Near-term Options for Treatment and Recyle Dr. Alan Hanson AREVA NC Inc. Executive Vice President, Technology and Used-Fuel Management American Nuclear Society Annual Meeting June 26, 2007 Boston, MA GNEP
More informationRecent progress in Advanced Actinide Recycling Processes
ECD Nuclear Energy Agency 11th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation Recent progress in Advanced Actinide Recycling Processes Dominique Warin CEA /
More informationGeneration IV International Forum: Update of the Technology Roadmap
Generation IV International Forum: Update of the Technology Roadmap Henri PAILLERE, NEA/Coordinator of the GIF Technical Secretariat High Level Workshop Launch of the NEA Nuclear Innovation 2050 OECD Conference
More informationRole of Partitioning and Transmutation (P&T) in Nuclear Energy
Role of Partitioning and Transmutation (P&T) in Nuclear Energy Kazufumi TSUJIMOTO Japan Atomic Energy Agency Nov. 6, 2013, Tokyo, Japan Topical Meeting embedded to INES-4 : International Nuclear Law Symposium
More informationPhase II Final Report of Feasibility Study on Commercialized Fast Reactor Cycle Systems. Executive Summary
Phase II Final Report of Feasibility Study on Commercialized Fast Reactor Cycle Systems Executive Summary March, 2006 Japan Atomic Energy Agency The Japan Atomic Power Company The Feasibility Study on
More informationCurrent options for the nuclear fuel cycle:
Current options for the nuclear fuel cycle: 1- Spent fuel disposal 2- Spent fuel reprocessing and Pu recovery Spent fuel and radiotoxicity 1/3 Composition of Spent Nuclear Fuel (Standard PWR 33GW/t, 10
More informationFast reactor development and worldwide cooperation in Generation-IV International Forum
Fast reactor development and worldwide cooperation in Generation-IV International Forum FR13 Paris, France March 4, 2013 Yutaka Sagayama Former Chair of the Generation-IV International Forum Senior Advisor
More informationFuel Recycling and MOX Production
Fuel Recycling and MOX Production Atoms for the Future Challenges of reactors and Fuel Cycle Projects Philippe KNOCHE AREVA CEO Used Nuclear Fuels Perspective and Challenges (1000 thm) LWR Used Fuel Inventories
More informationNuclear technology options
Nuclear technology options M.Salvatores Senior Scientific Advisor CEA, Nuclear Energy Division (France) and Idaho National Laboratory (USA) ATSE National Symposium 2013 Nuclear Energy for Australia? Thursday-Friday
More informationTrends in Transmutation Performance and Safety Parameters Versus TRU Conversion Ratio of Sodium-Cooled Fast Reactors
Trends in Transmutation Performance and Safety Parameters Versus TRU Conversion Ratio of Sodium-Cooled Fast Reactors The Tenth OECD Nuclear Energy Agency Information Exchange Meeting on Actinide and Fission
More informationNuclear Fuel Cycle Indian Scenario
Nuclear Recycle Group Nuclear Fuel Cycle Indian Scenario KAILASH AGARWAL Associate Director, NUCLEAR RECYCLE GROUP BHABHA ATOMIC RESEARCH CENTRE DEPARTMENT OF ATOMIC ENERGY MUMBAI, INDIA Advanced Fuel
More informationOECD Nuclear Energy Agency Activities Related to the Nuclear Fuel Cycle
International Symposium on Nuclear Back-end Issues and the Role of Nuclear Transmutation Technology Kyoto University, 28 November 2013 ECD Nuclear Energy Agency Activities Related to the Nuclear Fuel Cycle
More information2012 Deep River Science Academy Summer Lecture GENERATION IV SUPERCRITICAL WATER-COOLED REACTOR
2012 Deep River Science Academy Summer Lecture GENERATION IV SUPERCRITICAL WATER-COOLED REACTOR M. Yetisir Deep River, 2012 July 12 What is a Gen IV Reactor Contents How does nuclear plant work? What is
More informationSafety for the future Sodium cooled Fast Reactors
Safety for the future Sodium cooled Fast Reactors S. Beils a ; B. Carluec a ; N. Devictor b ; G.L. Fiorini b ; J.F. Sauvage c a AREVA / NP, 10 Rue Juliette Récamier, 69003 Lyon, France b CEA Cadarache,
More informationEquipment during fabrication and service: Safety, Competitiveness, Innovation. New requirements and R&D needs for future nuclear reactors
ESOPE 2007 European Symposium on Pressure Equipment Paris October 9-11 2007 Equipment during fabrication and service: Safety, Competitiveness, Innovation New requirements and R&D needs for future nuclear
More informationChallenges for nuclear power world-wide
Challenges for nuclear power world-wide wide Simposio Internacional Perspectivas Actuales de la Energia Nuclear Collegio Libre de Emeritos Madrid, 21-22 April 2008 Hans Forsström, Director Division of
More informationTechnology options for long term nuclear power development. A. Kakodkar, Chairman, Atomic Energy Commission INDIA
Technology options for long term nuclear power development A. Kakodkar, Chairman, Atomic Energy Commission INDIA 1 Long term nuclear power development - The challenge of the numbers. A per capita electricity
More informationGenIII/III+ Nuclear Reactors
OL1&2 GenII GenIII OL3 TVO s Olkiluoto Nuclear Power Plant in Finland GenIII/III+ Nuclear Reactors RESEARCH NEEDES AND CHALLENGES FISA 2009, Prague Contents What are the GenIII features Evolutionary development
More informationPROGRESS FOR THE CEA ALFA PROJECT
PROGRESS FOR THE CEA ALFA PROJECT V.ROYET B.Boullis,M.Boidron,C.Brenneis,F.Jorion,L.Donnet,P.Dehaudt,H.Lagrave Atalante Laboratory For Actinides bearing fuel manufacturing 1 CONTENT 1. Context 2. Atalante
More informationWith new solutions towards sustainable nuclear power: Gen-III, III+, and Gen-IV, as well as small- and medium size reactors (SMR)
With new solutions towards sustainable nuclear power: Gen-III, III+, and Gen-IV, as well as small- and medium size reactors (SMR) Imre Pázsit Chalmers University of Technology Nuclear Engineering HAS Scientific
More informationGeneration 3 Nuclear Reactors
Generation 3 Nuclear Reactors French- Slovak summer school The different generations of nuclear reactors From Generation-1 1 to Generation-4 G. Cognet CEA Delegate for Central Europe Nuclear Counsellor
More informationReadiness of Current and New U.S. Reactors for MOX Fuel
Readiness of Current and New U.S. Reactors for MOX Fuel North Carolina and Virginia Health Physics Societies Joint 2009 Spring Meeting New Bern, North Carolina 13 March 2009 Andrew Sowder, Ph.D., CHP Project
More informationPassive Complementary Safety Devices for ASTRID severe accident prevention
1 IAEA-CN245-138 Passive Complementary Safety Devices for ASTRID severe accident prevention M. Saez 1, R. Lavastre 1, Ph. Marsault 1 1 Commissariat à l Énergie Atomique et aux Énergies Alternatives (CEA),
More informationThe Generation IV Gas Cooled Fast Reactor
The Generation IV Gas Cooled Fast Reactor Dr Richard Stainsby AMEC Booths Park, Chelford Road, Knutsford, Cheshire, UK, WA16 8QZ Phone: +44 (0)1565 684903, Fax +44 (0)1565 684876 e-mail: Richard.stainsby@amec.com
More informationSafety of Advanced Nuclear Fuel cycles
Safety of Advanced Nuclear Fuel cycles Th. Fanghänel G. Cojazzi, N. Erdmann, D. Haas, R. Konings, V. Rondinella, J. Somers, P. van Uffelen European Commission Joint Research Centre Institute for Transuranium
More informationAdvanced Reactors Mission, History and Perspectives
wwwinlgov Advanced Reactors Mission, History and Perspectives Phillip Finck, PhD Idaho National Laboratory Senior Scientific Advisor June 17, 2016 A Brief History 1942 CP1 First Controlled Chain Reaction
More informationBACK-END SCENARIOS FOR THE FRENCH NUCLEAR FLEET
BACK-END SCENARIOS FOR THE FRENCH NUCLEAR FLEET Caroline DREVON Areva, Back-end Michel PAYS EDF, Fuel Cycle Division Bernard BOULLIS CEA, Nuclear Energy Division Sino-French Seminar Building up an Advanced
More informationnuclear science and technology
EUROPEAN COMMISSION nuclear science and technology Co-ordination and Synthesis of the European Project of Development of HTR Technology (HTR-C) Contract No: FIKI-CT-2000-20269 (Duration: November 2000
More informationNuclear Cogeneration
Nuclear Cogeneration International Workshop on Acceleration and Applications of Heavy Ions 26 February - 10 March 2012 Heavy Ion Laboratory, Warsaw, Poland Ludwik Pieńkowski Heavy Ion Laboratory University
More informationRecycling of UNF. Paul Murray
Recycling of UNF Paul Murray September 2016 Recycling of Commercial UNF is NOT the same as the operations that went on at Hanford. 96% of a used fuel assembly is recyclable Composition of used light water
More informationESNII. Concept Paper. The European Sustainable Nuclear Industrial Initiative
ESNII The European Sustainable Nuclear Industrial Initiative May 2010 A contribution to the EU Low Carbon Energy Policy: Demonstration Programme for Fast Neutron Reactors Concept Paper www.snetp.eu aaaaaaaaaaaaaaaa
More informationSFR systems R&D activities
SFR systems R&D activities Hiroki HAYAFUNE Chair of SFR-SSC GIF-INPRO Interface meeting 26-27 March 2018, IAEA HQ, Vienna System Integration & Assessment Project Slide 2 System Integration & Assessment
More informationWM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA. Opportunities for the Multi Recycling of Used MOX Fuel in the US
Opportunities for the Multi Recycling of Used MOX Fuel in the US - 12122 P. Murray*, F. Bailly**, E. Bouvier**, T. Gain**, F. Lelièvre**, G.H. Senentz**, and E. Collins*** *AREVA Federal Services LLC,
More informationVery High Temperature Reactor
Very High Temperature Reactor LI Fu GIF VHTR SSC Chair INET, Tsinghua University, China GIF Symposium San Diego November 15-16, 2012 Outline 1. Original VHTR Features 2. Key VHTR Development Targets 3.
More information