The FutureS of Nuclear Energy

Size: px
Start display at page:

Download "The FutureS of Nuclear Energy"

Transcription

1 The FutureS of Nuclear Energy Adrien Bidaud, Sylvain David, Olivier Méplan Groupe Physique des Réacteurs Laboratoire de Physique Subatomique et Corpusculaire IN2P3/CNRS Ecole Nationale Supérieure de Physique de Grenoble Institut National Polytechnique Grenoble A. Bidaud European Nuclear Physics Conference March

2 Paradoxes : A young «old» technology Are the uranium reserves already exhausted? Uranium resources When would breeders be needed? How fast can nuclear energy grow? Waste disposal : can we do something with the Montains of Nuclear Wastes lasting Million of years? What volumes and time period are we talking about? Do we need Undergroud repository? GEN IV ADS Is Civil use of Nuclear Energy linked to nuclear bomb proliferation? A. Bidaud European Nuclear Physics Conference March

3 A nuclear Restart? 1979 TMI (USA) Accident Level Oil Tchernobyl Barrel = 5$ Accident Level SuperPhénix Phénix stop refurbishment Current situation of nuclear Power is very diverse, in particular in Europe World tendance == Oil peak + Climate change = > 400 GWe (*2) proposed for 2030! And after?? A. Bidaud European Nuclear Physics Conference March

4 Potential of Generation II and III? Uranium consumption in a Light Water Reactor (LWR) U fissioned Enriched ( 238 U ~ 96%, 235 U ~ 4%) Natural ( 238 U ~ 99.3%, 235 U ~ 0.7%) /(GWe.y) Efficiency of resource utilization ~ 0.5 % Optimizations 1% reduction of 235 U loss in depleted U, increase the burn-up, re-treatment & re-enrichment of irradiated U 1 t 30 t 200 t è the knowledge of uranium resources should lead to an understanding of the production potential A. Bidaud European Nuclear Physics Conference March

5 Resources consumption World nuclear production World natural U comsumption 285 GWe (full power equiv.) 60,000 t/year (source NEA/OECD, 2006) Should we get prepared to an «uranium peak»? What is the definition of the resources? A. Bidaud European Nuclear Physics Conference March

6 URANIUM RESOURCES 1,00E+14 1,00E+13 Earth crust 1000 MtU/m ESTIMATED AMOUNT OF URANIUM (TONS) 1,00E+12 1,00E+11 1,00E+10 1,00E+09 1,00E+08 1,00E+07 1,00E+06 1,00E+05 1,00E+04 1,00E Conventional resources (identified) (< 130 US$/kg) 4.7 MtU VEIN DEPOSITS VEIN DEPOSITS PEGMATITES UNCONFORMITY DEPOSITS FOSSIL PLACERS SANDSTONES 1000 FOSSIL PLACERS SANDSTONES VOLCANIC DEPOSITS 100 BLACK SHALES SHALES PHOSPHATES 10 GRANITES AVERAGE CRUST 1 0,0001 A. Bidaud European Nuclear Physics Conference March EVAPORITES SILICEOUS OOZE CHERT OCEANIC IGNEOUS CRUST 0,1 ORE GRADE (PARTS PER MILLION OF URANIUM) 0,01 OCEAN WATER 0,001 Oceans 4500 MtU There will always be uranium. At what cost? FRESH WATER

7 Where is the Energy Cliff? 285 GWe (full power equiv.) ===== 60,000 t/year Resources U (reserves+rar+infered Resources) millions of tons?? Production Potential - at present rate (and use) years - scenario «nuclear x 8» & optimizations of U nat use in LWR years A. Bidaud European Nuclear Physics Conference March

8 Breeding But the production potential can change because of breeding 238 U + n 239 U 239 Np 239 Pu fertile fissile Also possible from 232 Th mass of Fissile produced Conversion Ratio CR = mass of Fissile destroyed CR 1 è Breeder CR < 1 è Burner (Self-)Breeding the fissioned Pu is regenerated (CR=1) : Pu mass = constant But U is consumed at a rate of 1 ton / (GWe.y) efficiency of resource utilization ~ 100 % More complex technology Higher investment costs è (200 x less than LWR) A. Bidaud European Nuclear Physics Conference March

9 Breeding & resources Price per kwh Breeder LWR Enriched U 130 $/kg >1000 $/kg Price defining U nat price the «ultimate» resources The discussion about resources is complicated The price triggering the economic competitiveness of breeders might be country specific A. Bidaud European Nuclear Physics Conference March

10 Which scenarios to studies? Installed Capacity Installed Capacity Need for breeders Uranium production time GEN IV (Na-FR? Thorium Molten Salt Fast Reactors?) Paradox : High initial fissile inventories (12t Pu / 1GWe Na- FR) :GEN IV deployment trigered by uranium fissile scarcity but strongly depends on fissile material availability! need for scenario studies Uranium production time No need for breeders Waste management (ADS?) Fissile material economy, use of Thorium in classical Water Reactors? Need for research on reactors involved in multi-strata scneraii Versatility of each stratum might be a very important issue Is Pu a waste? A. Bidaud European Nuclear Physics Conference March

11 CNPE Chinon ( -4 REP 900 MWe («GEN II») (close to «Châteaux de la Loire») - «la boule» : UNGG 70 MWe prototype («GEN I») A. Bidaud European Nuclear Physics Conference March

12 Generation IV Forum: selection of 6 nuclear systems Top-ranking and outsiders? Closed fuel cycle Sodium Fast Reactor Closed fuel cycle Lead Fast Reactor Closed fuel cycle Gas Fast Reactor Open fuel cycle Very High Temperature Reactor Open/Closed fuel cycle Super Critical Water Reactor Closed fuel cycle Molten Salt Reactor A. Bidaud European Nuclear Physics Conference March

13 Sodium cooled Fast Reactor SFR R&D (passive) Safety Design simplification (cost) MA Fuel fabrication Fast Spectrum Coolant: Na Very good coolant (& cheap) Low pressure Industrial experience but Chemically reactions with air/water/upuo 2 opaque Temperature: 550 C Fuel: Oxide or metal fuel Closed fuel cycle Pool layout SFR Compact loop SFR A. Bidaud European Nuclear Physics Conference March

14 Did GEN IV existed before GEN II? EBR I ( ) (Experimental Breeder Reactor) first nuclear reactor connected to the grid! SuperPhénix ( ) France has expericence of dismantling a 1200MWe Sodium breeder reactor but none for PWR!!! Communication is ALWAYS very oriented when energy issue is involved A. Bidaud European Nuclear Physics Conference March

15 thorium cycle using Molten Salt Reactors Concept Molten Salt Fast Reactor (MSFR) Negative reactivity coefficients Various possible fuel : Th/U (equilibrium) BUT also Th/Pu+AM : direct transgition gen3 MSFR Starting inventory for 1 GWe Th : 37 tonnes Pu fissile : 8.4 tonnes taux d'incinération des TRU (%) Th/Pu Th/U Transition GEN III Trans-Uranium incineration année après démarrage A. Bidaud European Nuclear Physics Conference March

16 Scenario A: breeders are needed Is it possible to start breeder reactors? Fissile Inventory/GWe SFR ~ 12t of Pu è mass of Pu produced after 50 years of a 1 GWe LWR LFR ~ 16t of Pu GFR ~ 20t of Pu Fast MSR ~ 6t of 233 U / 8t of Pu Thermal MSR ~ 2t of 233 U Example: 60 GWe of French LWR 60 GWe of breeder (SFR) equilibrium Pu inventory in a SFR fleet = 800 tons available Pu inventory in 2002 = 220 tons è 30% of the needed inventory A. Bidaud European Nuclear Physics Conference March

17 Scenario B without Gen IV (no breeding) Ø Scenario B : the role of ADS Pu in LWR, MA in ADS Proton beam LWR Innovative partitioning Am, Cm ADS 90% 10% Am, Cm U, Pu FP HLW FP +0.1% Pu +0.1% Np, Am, Cm A. Bidaud European Nuclear Physics Conference March

18 Waste management : the french case the «Loi Bataille(30/12/1991)» defined 3 research avenues for 15 years : Axe 1 : «Séparation/Transmutation» Axe 2 : «Deep geological repository» Axe 3: «long-term sub-surface storage» The «new» law claimed these axis to be «complementary» A. Bidaud European Nuclear Physics Conference March

19 Mountains of Nuclear Wastes lasting millions of years? 1 assembly == 500 Kg U == T Coal 20t/an/GWe * 60 in France = 120T/years /360 days a year = 330kg/ day of spent fuel arriving La Hague reprocessing plant No mountains close to La Hague A. Bidaud European Nuclear Physics Conference March

20 Accelerator Driven System ADS Fast spectrum Pure MA (Np, Am, Cm) fuels can be used not possible in critical reactors (temperature effect, lack of delayed neutrons) Need an external neutron source to drive the sub-critical core Source RFQ Injector Accelerator Supra cavities Protons beam 1 GeV ma 0.1 ev 20 MeV 1 GeV R&D Accelerator reliability Beam window Coupling spallation target/core Design MA Fuel fabrication A. Bidaud European Nuclear Physics Conference March

21 Scenario B with Gen IV (no breeding) Ø Scenario B : FNR burner Pu+MA incineration in FNR LWR Innovative partitioning Pu, MA Burner FNR U depleted FP 80% 20% U, Pu, MA Innovative partitioning HLW +0.1% Pu +0.1% Np, Am, Cm FP A. Bidaud European Nuclear Physics Conference March

22 Transmutation 300 tons MA in HLW S1: w/o transmutation S3: transmutation in MA S3 = MA S2 X S2: transmutation in 2040 Transmutation: interesting for the long term Delayed transmutation (or partitioning) reduces the transmutation gain tons tons MA in HLW scenario S1 scenario S2 MA in fuel cycle A. Bidaud European Nuclear Physics Conference March

23 Scenario B to Scenario A: symbiotic fleet Goal: Pu incineration without forbidding a transition to a breeding fleet in a long time Stage 1: enough Uranium, No need of breeding The role of Thorium in solid fuel LWR Pu,MA FP 80% 20% HLW FP FNR U, Pu, MA Stage 2: symbiotic fleet : globally self-breeding Th/ 233 U 233 U (400kg/GWe) FNR Pu+MA burner Evolutive technology High Convertion Ratio reactor ~ 0.9 (BWR, HWR, ) 80% FP 20% HLW FP U, Pu, MA Self-breeder U/Pu core +Th blanket A. Bidaud European Nuclear Physics Conference March

24 Proliferation issue Non proliferation Treaty : only 5 countries have the right to have the bomb The other should open their facilities to IAEA inspectors => NO one complying the Treaty is suspected to possess bombs : big success! Only 4 countries does not signed it (and have the bomb) : India, Pakistan, Israel, North Korea Iran does not comply with its obligations Are they building bombs? No reactor or facility build for Civil applications and visited by IAEA has been used for proliferation Conclusion : help public opinion, make Treaty success known, support IAEA!!! A. Bidaud European Nuclear Physics Conference March

25 Conclusion (Nuclear) future is very difficult to forecast! Nuclear power will probably increase very fast in the next decades BUT will probably not fuel our cars in 2050 Nuclear futures are very different depending on each country choices : waste disposal safety regulations (Na-FR?) Research (technology availability) uranium market independence (ex: India) Knowledge management Nuclear Physicist are involved in research (ADS, GEN IV ) and should help in giving scientific arguments to the (policial) debate A. Bidaud European Nuclear Physics Conference March

The Nuclear Fuel Cycle Lecture 5

The 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 information

Generation IV Roadmap: Fuel Cycles

Generation IV Roadmap: Fuel Cycles Generation IV Roadmap: Fuel Cycles Fuel Cycle Crosscut Group (FCCG) Generation IV Roadmap Session ANS Winter Meeting Reno, NV November 13, 2001 1 FCCG Members Arden Bement Purdue University Charles Boardman

More information

Thorium an alternative nuclear fuel cycle

Thorium an alternative nuclear fuel cycle Thorium an alternative nuclear fuel cycle 5th Smart Grids & Clean Power Conference, Cambridge, 5 June 2013 www.cir-strategy.com/events/cleanpower Kevin Hesketh, Senior Research Fellow Outline General Principles

More information

The Thorium Fuel Cycle

The Thorium Fuel Cycle The Thorium Fuel Cycle ThEC13 Daniel Mathers daniel.p.mathers@nnl.co.uk Outline Content: Background Sustainability, proliferation resistance, economics, radiotoxicity Advantages and disadvantages Fuel

More information

IAEA/JAEA INTERNATIONAL WORKSHOP

IAEA/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 information

Considerations for a Sustainable Nuclear Fission Energy in Europe

Considerations 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 information

Radiochemistry Webinars

Radiochemistry 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 information

The Tube in Tube Two Fluid Approach

The Tube in Tube Two Fluid Approach The Tube in Tube Two Fluid Approach March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com

More information

The DMSR: Keeping it Simple

The DMSR: Keeping it Simple The DMSR: Keeping it Simple March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com What

More information

The Nuclear Fuel Cycle Simplified

The 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 information

Workshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at

Workshop 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 information

Role of Partitioning and Transmutation (P&T) in Nuclear Energy

Role 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 information

RECYCLING 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 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 information

-What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES?

-What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES? Thorium Energy Alliance Conference March 29-30, 2010, Mountain View, CA, USA: -What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES? (Establishing (Establishing SIMPLEST SIMPLEST

More information

Current options for the nuclear fuel cycle:

Current 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 information

Generation IV Reactors

Generation 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 information

Energy from nuclear fission

Energy from nuclear fission Energy from nuclear fission M. Ripani INFN Genova, Italy Joint EPS-SIF International School on Energy 2014 Plan Figures about nuclear energy worldwide Safety Reaction products Radioactive waste production

More information

The Legacy of U.S. Energy Leadership

The 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 information

Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR

Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com

More information

Nuclear Energy. Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology

Nuclear Energy. Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology Nuclear Energy Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology NAE Symposium The Role of Alternative Energy Sources in a Comprehensive

More information

International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015

International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015 International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015 Feasibility and Deployment Strategy of Water Cooled Thorium Breeder Reactors Naoyuki Takaki Department of

More information

ADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES. M. Salvatores CEA-DRN Bât. 707 CE/Cadarache Saint-Paul-Lez-Durance Cedex France.

ADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES. M. Salvatores CEA-DRN Bât. 707 CE/Cadarache Saint-Paul-Lez-Durance Cedex France. ADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES M. Salvatores CEA-DRN Bât. 707 CE/Cadarache 13108 Saint-Paul-Lez-Durance Cedex France Abstract Advanced options for transmutation strategies currently investigated

More information

Department of Nuclear Energy. Division of Nuclear Power. Nuclear Power. International Atomic Energy Agency. Akira OMOTO IAEA

Department of Nuclear Energy. Division of Nuclear Power. Nuclear Power. International Atomic Energy Agency. Akira OMOTO IAEA Nuclear Power Akira OMOTO Division of Nuclear Power Department of Nuclear Energy IAEA International Atomic Energy Agency blank page.doc 40/1000mm 35/1000mm 40/1000mm 95/1000mm What is nuclear fission?

More information

Near-term Options for Treatment and Recyle

Near-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 information

The Potential for Nuclear Energy in the UK Beyond 2025

The Potential for Nuclear Energy in the UK Beyond 2025 The Potential for Nuclear Energy in the UK Beyond 2025 Dan Mathers Business Leader - Fuel and Radioisotope Technology World Nuclear New Build Congress London, September 2014 Scenarios for UK deployment

More information

Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES)

Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES) Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES) Ritsuo Yoshioka (*1), Koshi Mitachi (*1) & Motoyasu Kinoshita(*1,2) (*1) International Thorium Molten-Salt Forum (*2)University of Tokyo

More information

Abundant and Reliable Energy from Thorium. Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015

Abundant and Reliable Energy from Thorium. Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015 Abundant and Reliable Energy from Thorium Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015 This is incorrect. Nuclear energy is our greatest hope for the future. Nuclear energy contains over

More information

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona USA

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona USA The Potential Role of the Thorium Fuel Cycle in Reducing the Radiotoxicity of Long-Lived Waste 13477 Kevin Hesketh and Mike Thomas The UK s National Nuclear Laboratory, Preston Laboratory, Preston, PR4

More information

Closed Fuel Cycle Strategies and National Programmes in Russia

Closed 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 information

Fuel Recycling and MOX Production

Fuel 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 information

The Integral Fast Reactor/Prism: a social & climate change perspective

The Integral Fast Reactor/Prism: a social & climate change perspective The Integral Fast Reactor/Prism: a social & climate change perspective Mark Lynas Environmentalist and author, The God Species Climate change July hottest month ever in USA Arctic ice melt heading for

More information

Plutonium Management in France. Current Policy and Long Term Strategy for the Used Fuel Recycling by LWR and Fast Reactors

Plutonium 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 information

Current Situation of MSR Development in Japan. Yoichiro SHIMAZU Graduate School of Engineering Hokkaido University, Japan

Current Situation of MSR Development in Japan. Yoichiro SHIMAZU Graduate School of Engineering Hokkaido University, Japan Current Situation of MSR Development in Japan Yoichiro SHIMAZU Graduate School of Engineering Hokkaido University, Japan 1 Related Organizations International Thorium Molten-Salt Forum (ITHMSF ) President:

More information

IMPACT OF A PROGRESSIVE DEPLOYMENT OF FAST REACTORS IN A PWR FLEET

IMPACT 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 information

A Strategy for the Nuclear Fuel Cycle in the 21st Century

A Strategy for the Nuclear Fuel Cycle in the 21st Century A Strategy for the Nuclear Fuel Cycle in the 21st Century uji. Kazim assachuse s Ins tu of Technolog A lecture for The ANS Chapter in Austria The IAEA, Vienna, Austria May 26, 2009 MIT Center for Advanced

More information

Nuclear power. ME922/927 Nuclear 1

Nuclear power. ME922/927 Nuclear 1 Nuclear power ME922/927 Nuclear 1 The process The production of electricity by nuclear fission. Torness power station The impact of a neutron with a U 235 nucleus causes the fission process, from which

More information

THE FRENCH PROGRAM FOR A SUSTAINABLE MANAGEMENT OF NUCLEAR MATERIALS AND WASTE

THE 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 information

Impact of partitioning and transmutation on nuclear waste management and the associated geological repositories

Impact of partitioning and transmutation on nuclear waste management and the associated geological repositories Impact of partitioning and transmutation on nuclear waste management and the associated geological repositories Enrique M. González-Romero CIEMAT, Madrid, Spain Summary Recent Eurobarometers show that

More information

Advanced and innovative reactor concept designs, associated objectives and driving forces

Advanced 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 information

Module 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria

Module 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 information

NEXT STEP FOR NUCLEAR POWER PLANT GENERATION IV

NEXT 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 information

Fast and High Temperature Reactors for Improved Thermal Efficiency and Radioactive Waste Management

Fast 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 information

JAEA s Efforts for Reduction of Radioactive Wastes

JAEA 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 information

Modular Helium-cooled Reactor

Modular Helium-cooled Reactor Modular Helium-cooled Reactor The role of the GTMHR in GNEP E. Michael Campbell Francesco Venneri General Atomics April 2007 SEMA Conference 1 OUTLINE Motivation High Temperature gas reactors MHR as burner

More information

Transmutation of nuclear wastes by metal fuel fast reactors

Transmutation of nuclear wastes by metal fuel fast reactors PSN Number: PSNN-2014-0979 Document Number: AFT-2014-000359 Rev.000(0) Transmutation of nuclear wastes by metal fuel fast reactors International Symposium on Present Status and Future Perspective for Reducing

More information

The role of nuclear power in Janne Wallenius Professor Reactor Physics, KTH

The 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 information

The role of thorium in UK nuclear R&D

The role of thorium in UK nuclear R&D The role of thorium in UK nuclear R&D Current trends and MSFR modelling 28 th October 2013, ThEC 2013, CERN The role of thorium in UK nuclear R&D Analysis of UK nuclear R&D strategy. The role of fuel cycle

More information

Trends 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 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 information

Dynamic Analysis of Nuclear Energy System Strategies for Electricity and Hydrogen Production in the USA

Dynamic Analysis of Nuclear Energy System Strategies for Electricity and Hydrogen Production in the USA Dynamic Analysis of Nuclear Energy System Strategies for Electricity and Hydrogen Production in the USA L. Van Den Durpel, D. C. Wade, H. Khalil, A. Yacout Nuclear Engineering Division, Argonne National

More information

Chemical Engineering 412

Chemical Engineering 412 Chemical Engineering 412 Introductory Nuclear Engineering Lecture 20 Nuclear Power Plants II Nuclear Power Plants: Gen IV Reactors Spiritual Thought 2 Typical PWR Specs Reactor Core Fuel Assembly Steam

More information

Composition of Spent Nuclear Fuel (Standard PWR 33GW/t, 10 yr. cooling)

Composition of Spent Nuclear Fuel (Standard PWR 33GW/t, 10 yr. cooling) Spent fuel and radiotoxicity 1/3 Composition of Spent Nuclear Fuel (Standard PWR 33GW/t, 10 yr. cooling) 1 tonne of SNF contains: 955.4 kg U 8,5 kg Pu Minor Actinides (MAs) 0,5 kg 237 Np 0,6 kg Am 0,02

More information

Japan Revival Strategy by Thorium MSR

Japan Revival Strategy by Thorium MSR Japan Revival Strategy by Thorium MSR Takashi Kamei Ritsumeikan University, Kyoto, Japan HAE00675@nifty.com Thank you to all. We are facing lots of problems Transportation Power generation Global warming

More information

U.S. DOE currently has a number of initiatives to promote the growth of nuclear energy

U.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 information

BACK-END SCENARIOS FOR THE FRENCH NUCLEAR FLEET

BACK-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 information

Accelerator Driven Systems. Dirk Vandeplassche, Luis Medeiros Romão

Accelerator Driven Systems. Dirk Vandeplassche, Luis Medeiros Romão Accelerator Driven Systems Dirk Vandeplassche, Luis Medeiros Romão IPAC'12, New Orleans (Louisiana) May 21, 2012 1 Overview 1. Introduction 2. The accelerator for ADS 3. Projects 4. Concluding remarks

More information

Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor

Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor Oct 25 th 2007 Presentation to the Ottawa Chapter of the Canadian Nuclear Society Dr. David LeBlanc Physics Department

More information

Disposing High-level Transuranic Waste in Subcritical Reactors

Disposing High-level Transuranic Waste in Subcritical Reactors Disposing High-level Transuranic Waste in Subcritical Reactors Yaosong Shen Institute of Applied Physics and Computational Mathematics, 6 Huayuan Road, 100088, Beijing, China We propose a new method of

More information

Seminar 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 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 information

WM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA. Opportunities for the Multi Recycling of Used MOX Fuel in the US

WM2012 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 information

Recent Research Activities on Thorium and MSR in Japan

Recent Research Activities on Thorium and MSR in Japan Recent Research Activities on Thorium and MSR in Japan Takashi Kamei Research Institute for Applied Sciences, Researcher 49, Tanaka-Oi-cho, Sakyo-ku, Kyoto, 606-8202, JAPAN E-Mail: hae00675@nifty.com Introduction

More information

Role of the Fast Reactor and Efforts on Monju

Role 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 information

Nuclear Fuel Cycle Transition Scenario Studies

Nuclear Fuel Cycle Transition Scenario Studies Nuclear Science ISBN 978-92-64-99068-5 Nuclear Fuel Cycle Transition Scenario Studies Status Report OECD 2009 NEA No. 6194 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT FOREWORD

More information

COE-INES-1 CORE CONCEPT OF COMPOUND PROCESS FUEL CYCLE

COE-INES-1 CORE CONCEPT OF COMPOUND PROCESS FUEL CYCLE COE-INES-1 CORE CONCEPT OF COMPOUND PROCESS FUEL CYCLE Objectives # Proposal of innovative nuclear fuel cycle system - economic competitiveness - efficient utilization of nuclear fuel resources - reduction

More information

Safeguard and protection requirements for Gen-IV reactor systems

Safeguard and protection requirements for Gen-IV reactor systems Matthew Gill 25/03/13 Matthew.gill-2@postgrad.manchester.ac.uk Safeguard and protection requirements for Gen-IV reactor systems 1 Content 1. Gen-IV reactors Concepts and Advantages TRL and contribution

More information

Closing the fuel cycle and Managing nuclear waste

Closing 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 information

Nuclear Power Plants

Nuclear Power Plants NUCLEAR ENERGY 2.0 500 times more energy 1000 times less waste Dr Jan Leen Kloosterman Assoc. Prof Nuclear Reactor Physics Head of Section Physics of Nuclear Reactors Program Director of Sustainable Energy

More information

The Nuclear Fuel Cycle Lecture 4

The 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 information

Fast Thorium Molten Salt Reactors started with Plutonium

Fast Thorium Molten Salt Reactors started with Plutonium Author manuscript, published in "ICAPP '06 : International Congress on Advances in Nuclear Power Plants, Reno, Nevada : United Proceedings of ICAPP 06 States" Fast Thorium Molten Salt Reactors started

More information

DOE Activities Promoting Understanding of Advanced Nuclear Fuel Cycles

DOE Activities Promoting Understanding of Advanced Nuclear Fuel Cycles DOE Activities Promoting Understanding of Advanced Nuclear Fuel Cycles Patricia Paviet Director for Systems Engineering and Integration (NE-51) Office of Fuel Cycle Technologies Office of Nuclear Energy

More information

Future nuclear systems: fuel cycle options and guidelines for research

Future 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 information

Thorium Fuel Cycle Activities in IAEA

Thorium Fuel Cycle Activities in IAEA Thorium Fuel Cycle Activities in IAEA Uddharan Basak Nuclear Fuel Cycle and Material Section Division of Nuclear Fuel Cycle and Waste Technology Department of Nuclear Energy IAEA 1 International Atomic

More information

Transmutation. Janne Wallenius Professor Reactor Physics, KTH. ACSEPT workshop, Lisbon

Transmutation. 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 information

Advanced Reactors Mission, History and Perspectives

Advanced 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 information

The Future of the Nuclear Fuel Cycle

The Future of the Nuclear Fuel Cycle The Future of the Nuclear Fuel Cycle Results* and Personal Observations Charles W. Forsberg Executive Director MIT Nuclear Fuel Cycle Study Department of Nuclear Science and Engineering cforsber@mit.edu

More information

Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar

Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar Fusion Power Program Technology Division Argonne National Laboratory 9700 S. Cass Avenue, Argonne, IL 60439,

More information

Nuclear technology options

Nuclear 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 information

Importance of materials for sustainable nuclear energy

Importance of materials for sustainable nuclear energy Common EESC-EERA Event / EUSEW 2012 Brussels, 18 June 2012 Importance of materials for sustainable nuclear energy L. Malerba - SCK CEN Joint Programme Nuclear Materials SubProgramme coordinator (on behalf

More information

Nuclear Waste: How much is produced, and what can be used

Nuclear Waste: How much is produced, and what can be used Nuclear Waste: How much is produced, and what can be used Physics of Nuclear Reactors Faculty of Applied Sciences Delft University of Technology Products from fission Material balance in fuel cycle (1

More information

Long term trends in nuclear production technologies. Noel Camarcat

Long 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 information

The 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 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 information

Nuclear energy in Europe

Nuclear energy in Europe Nuclear energy in Europe Contribution to the Future Low Carbon Energy Society Dr. Ákos Horváth Director General, MTA Centre for Energy Research (HU) akos.horvath@energia.mta.hu EASAC/JRC meeting on Nuclear

More information

Fast Reactor Development in France

Fast 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 information

Fusion-Fission Hybrid Systems

Fusion-Fission Hybrid Systems Fusion-Fission Hybrid Systems Yousry Gohar Argonne National Laboratory 9700 South Cass Avenue, Argonne, IL 60439 Fusion-Fission Hybrids Workshop Gaithersburg, Maryland September 30 - October 2, 2009 Fusion-Fission

More information

Molten-Salt Reactor FUJI and Related Thorium Cycles

Molten-Salt Reactor FUJI and Related Thorium Cycles Thorium Energy Alliance Spring Conference 2010, March 29-30, 2010, Mountain View, USA 1 Molten-Salt Reactor FUJI and Related Thorium Cycles Ritsuo Yoshioka (Presenter)* K. Furukawa, Y. Kato, K. Mitachi

More information

Synergistic Spent Nuclear Fuel Dynamics Within the European Union. Jin Whan Bae, Kathryn Huff, Clifford Singer 1

Synergistic Spent Nuclear Fuel Dynamics Within the European Union. Jin Whan Bae, Kathryn Huff, Clifford Singer 1 261 Synergistic Spent Nuclear Fuel Dynamics Within the European Union Jin Whan Bae, Kathryn Huff, Clifford Singer 1 1 Dept. of Nuclear, Plasma, and Radiological Engineering, University of Illinois at Urbana-Champaign

More information

Critique of The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study (2011)

Critique of The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study (2011) Critique of The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study (2011) Developed by the Science Council for Global Initiative Contact: Tom Blees 1. The Study

More information

Perspectives of Partitioning and Transmutation Technology. H. Oigawa Japan Atomic Energy Agency

Perspectives of Partitioning and Transmutation Technology. H. Oigawa Japan Atomic Energy Agency Perspectives of Partitioning and Transmutation Technology H. Oigawa Japan Atomic Energy Agency 1 Partitioning and Transmutation (P&T) Spent fuel Reprocessing FP MA U Pu MA (Np, Am, Cm) Geological disposal

More information

NUCLEAR ENERGY IN FRANCE ACHIEVEMENTS MAIN PROSPECTS AND CHALLENGES

NUCLEAR ENERGY IN FRANCE ACHIEVEMENTS MAIN PROSPECTS AND CHALLENGES NUCLEAR ENERGY IN FRANCE ACHIEVEMENTS MAIN PROSPECTS AND CHALLENGES Bernard Tinturier (EDF Presidency) and Michel Debes (EDF Fuel Division) email: michel.debes@edf.fr) 1 NUCLEAR POWER IN FRANCE France,

More information

FRENCH WASTE MANAGEMENT STRATEGY FOR A SUSTAINABLE DEVELOPMENT OF NUCLEAR ENERGY

FRENCH 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 information

Next Generation Nuclear Reactors

Next 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 information

Mathematical Modelling of Regional Fuel Cycle Centres

Mathematical Modelling of Regional Fuel Cycle Centres Mathematical Modelling of Regional Fuel Cycle Centres by Leonard L. Bennett and Larry D. Reynolds The concept of Regional Fuel Cycle Centres (RFCC) has attracted wide interest as a possible approach towards

More information

FOR A FUTURE WE CAN BELIEVE IN. International Thorium Energy Conference 2015

FOR A FUTURE WE CAN BELIEVE IN. International Thorium Energy Conference 2015 FOR A FUTURE WE CAN BELIEVE IN International Thorium Energy Conference 2015 ( 10-13 - 2015 ) LFTR: In search of the Ideal Pathway to Thorium Utilization Development Program Update. Current Status Benjamin

More information

COSI6 A Tool for Nuclear Transition Scenarios studies

COSI6 A Tool for Nuclear Transition Scenarios studies COSI6 A Tool for Nuclear Transition Scenarios studies G. Krivtchik, R. Eschbach, G. Martin, M. Tiphine, D. Freynet, R. Girieud, P. Miranda Atomic Energy and Alternative Energies Commission CEA, DEN, Cadarache,

More information

Influence of Fuel Design and Reactor Operation on Spent Fuel Management

Influence of Fuel Design and Reactor Operation on Spent Fuel Management Influence of Fuel Design and Reactor Operation on Spent Fuel Management International Conference on The Management of Spent Fuel from Nuclear Power Reactors 18 June 2015 Vienna, Austria Man-Sung Yim Department

More information

Innovative systems for sustainable nuclear energy generation and waste management

Innovative systems for sustainable nuclear energy generation and waste management Journal of Physics: Conference Series Innovative systems for sustainable nuclear energy generation and waste management To cite this article: Jm Loiseaux and S David 2006 J. Phys.: Conf. Ser. 41 36 View

More information

FUTURE NUCLEAR FUEL CYCLES: GUIDELINES

FUTURE 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 information

Japanese FR Deployment Scenario Study after the Fukushima Accident

Japanese FR Deployment Scenario Study after the Fukushima Accident FR13, Paris, France, 4-7 March 213 Japanese FR Deployment Scenario Study after the Fukushima Accident Kiyoshi ONO Hiroki SHIOTANI, Akira OHTAKI, Kyoko MUKAIDA and Tomoyuki ABE Japan Atomic Energy Agency

More information

Systematic Evaluation of Uranium Utilization in Nuclear Systems

Systematic Evaluation of Uranium Utilization in Nuclear Systems Systematic Evaluation of Uranium Utilization in Nuclear Systems Taek K. Kim and T. A. Taiwo 11 th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation San Francisco,

More information

European Vision in P&T. Advances in Transmutation Technology

European Vision in P&T. Advances in Transmutation Technology European Vision in P&T Advances in Transmutation Technology Prof. Dr. Hamid Aït Abderrahim SCK CEN, Boeretang 200, 2400 Mol, Belgium haitabde@sckcen.be or myrrha@sckcen.be Copyright 2010 SCK CEN 1 After

More information