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CNRS and IN2P3 in short. CNRS of France is the largest European Research Organisation, operating in all fields of science & technology IN2P3 and INSU are the two historical "national Institutes", the French government wants now to extent this model of organisation
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CNRS and IN2P3 in short CNRS of France is the largest European Research Organisation, operating in all fields of science & technology IN2P3 and INSU are the two historical "national Institutes", the French government wants now to extent this model of organisation to the other fields of science by creation additional institutes within CNRS. IN2P3, as its name says is reponsible to coordinate and fund all the academic research in Nuclear and Particle Physics and their Related applications Meeting with WUT, Warsaw, 6 January 2009
Present Scientific Priorities of IN2P3 • Red = Accelerators involved!! • Focus HEP activities at CERN, based on LHC and its developments • Further develop GANIL as the European Research Center with the most intense exotic nuclear beams based on new SPIRAL2 project • (Construction relying on SUPRATECH and ALTO-testbench) • Be a major player for (initial, conceptual) R&D in the field of nuclear energy based on our PACEN programme (e.g. ADS, Th-fuel technology..) • Further consolidate our presence in and our relations • - to the fields of Astrophysics and Cosmology ("astroparticles"), • - to the field of computing and other applications based on • the "grid" (LCG et EGEE) • Further amplify our commitments to forefront accelerator R&D • (i.e. EURISOL, Nufact, CLIC, ILC, ATF2 and laser-plasma techniques) • Research in instrumentation in general and associated technology transfer • (includes e.g. proton/hadrontherapy) Meeting with WUT, Warsaw, 6 January 2009
L'IN2P3, quelques chiffres • Plus que 2500 personnes, dont : • 417 Chercheurs CNRS de la section 03 • 90 Chercheurs CNRS des autres sections • Enseignants-chercheurs et chercheurs non CNRS • 250 Personnels techniques et administratifs non CNRS • 1477 Personnels techniques et administratifs CNRS • Repartition Géographique : • 1058 Ile de France • 504 Rhône Alpes • 313 Normandie • Alsace • Provence • Centre • 97 Bretagne – Pays de Loire • Aquitaine – Limousin • 44 Languedoc Roussillon Meeting with WUT, Warsaw, 6 January 2009
Growth in World Energy Demand ("typical" predictions) also "typical": electricity=1/3 of primary Nuclear share of electricity: 17% world-wide 35% Europe 80% France Meeting with WUT, Warsaw, 6 January 2009
Cumulated CO2 emissions from different means of electricity production • Production Mode grams CO2 /kWh • Hydro-electricity 4 • Nuclear 6 • Wind 3-22 • Photovoltaic 60-150 • Combined-cycle gas turbine 427 • Natural gas direct-cycle 883 • Fuel 891 • Coal 978 Range reflects the assumption on how the large amount of energy for making the systems is generated!! Source: SFEN, ACV-DRD Study Meeting with WUT, Warsaw, 6 January 2009
120% 100% 80% Life Cycle Emissions relative to Lignite 60% 40% 20% 0% CO2 SO2 NOx PM10 Coal (43 %) Lignite (40 %) Gas CC (57.6 %) Nuclear (PWR ult.waste dis.) PV (5 kW, poly) PV (5 kW, amorphous) Wind (1 MW; 5.5 m/s) Wind (1 MW; 4.5 m/s) Hydro (3.1 MW) Life Cycle Emissions From A. Voss (IER Stuttgart) Meeting with WUT, Warsaw, 6 January 2009
What is "Sustainability" • We must consider our planet to be on loan from our children, rather than being a gift from our ancestors. (...) As caretakers of our common future, we have the responsibility to seek scientifically sound policies, nationally as well as internationally. If the long-term viability of humanity is to be ensured, we have no other choice. • (Gro Harlem Brundtland) • Definitions from the Brundtland Commission: • Sustainable Development is development that meets the needs of the present without compromising the ability of future generations to meet their own needs". • It’s a process of change in which the exploitation of resources, • the direction of investments, the orientation of technological development and institutional change are made consistent with • future as well as present needs. Meeting with WUT, Warsaw, 6 January 2009
Measuring Sustainability • Sustainability of an energy producing system can be • measured by costs if all costs are considered. • all costs = internal + external (use of environment) • hence, management rules (from Voss 2005) • The supply of energy services shall be carried out with • the possibly lowest total costs. • Total costs represent a useful measure for the usage of • scarce resources. • Therefore they are an indicator for relative sustainability • of technologies and systems for supplying energy. • Research and development are the basis for improving • efficiencies for usage of resources, for limiting energy • caused environmental impacts and for expanding the • technical-economical energy-basis for future generations. Meeting with WUT, Warsaw, 6 January 2009
Total life cycle raw material requirements Source: Marheineke 2002 Meeting with WUT, Warsaw, 6 January 2009
Inspite of being unable to meet Kyoto 2010 objectives, le federal Gvt fixes for 2020 an even more ambitious objective: -40% MTeqCO2 in 2020. MTequ.CO2 -0.6% Yet, if the presenty adopted measures are to be maintained, one may land here ("common sense" extra- Polation by H. Flocard) . Black point = DFG analysis (taking into account the phase-out of nuclear power as presently Imposed by law) The German Plan Political Fiction (2020 = -40%) Red Point: Flocard extrapolation And continuation of Nuclear Power at present level Meeting with WUT, Warsaw, 6 January 2009
some numbers for France……, giving a hint where to go • better insulation, heat pumps…. • electric cars • urban short distance compatible • with battery technology • intermodal transport • use much more electricity • synthetic fuel • from "wet" and "waste" biomass • Fischer-Tropsch + addtl. H2 • considerably increase • electricity production • up to 50% more nuclear • some potential for intermittent • technologies (wind, solar), mainly • for H2 production = storage • problem efficiently taken • into account quoted from CEA/HC Meeting with WUT, Warsaw, 6 January 2009
Generation II Generation I • LWR-PWR, BWR • CANDU • HTGR/AGR • VVER/RBMK • Early prototype/demo reactors • Shippingport • Dresden, Fermi I • Magnox Generation IV • Highly economical • Proliferation resistant • Enhanced safety • Minimize waste • First demo of nuclear power on commercial scale • Close relationship with DOD • LWR dominates • Multiple vendors • Custom designs • Size, costs, licensing times driven up Generations of nuclear power plants Generation III • ABWR, System 80+, AP600, EPR • Passive safety features • Standardized designs • Combined license from van Heek Groningen Energy Convention 2005 Atoms for Peace TMI-2 Chernobyl 1950 1960 1970 1980 1990 2000 Meeting with WUT, Warsaw, 6 January 2009
Nuclear energy makes 880 TWh/y (35% of EU's electricity), but PWR produce important amounts of high level waste • Nuclear Waste from • present LWR's • (Light Water Reactors) • is highly radiotoxic (108 Sv/ton) • at the end of present- type nuclear deployment about 0.3 Mtons, or 3x1013 Sv, compare to radiation workers limiting dose of 20mSv • the initial radiotoxicity level of the mine is reached after more than 1 Mio years • worldwide, at present 370 "1GWel equiv. LWR" produce 16% of the net electricity • Geologic time storage of spent fuel is heavily debated • leakage in the biosphère ? • expensive (1000 €/kg), sites? (Yucca mountain would hold 0.07 Mio tons!!) • public opposition Meeting with WUT, Warsaw, 6 January 2009
The Yucca Mountain Dilemma • In the United States, the current plan is to send all spent nuclear fuel to the • Yucca Mountain Repository. The challenge they are faced with is that new • repositories will be needed as nuclear energy continues or grows. Speaker @ Yucca Mountain M. Capiello & G. Imel (ANL) (ICRS-10/RPS2004) EIA 1.5% Growth MIT Study 6-Lab Strategy Spent Fuel (metric tons) Secretarial Recommendation on second repository Constant 100 GWe Capacity based on limited exploration Year Legislatedcapacity Meeting with WUT, Warsaw, 6 January 2009
2 1,5 1 0,5 0 -0,5 Pu240 D(TRU) D(Pu) Pu241 -1 Pu238 Np237 Pu242 Am243 Cm244 Pu239 Am242 U238 -1,5 -2 Cm245 -2,5 -3 Neutron consumption per fission ("D-factor") for thermal (red) and fast (blue) neutron spectra • D 0 implies a source of neutrons is required, • whereas D < 0 implies excess neutron self-production Sustainability = Fast Neutrons Meeting with WUT, Warsaw, 6 January 2009
Fermeture du cycle du combustible par ADS Incinération des déchets radioctifs • L’incinération des déchets, donc de combustible hautement enrichi en actinides mineurs par un système sous critique n’est pas vertu mais nécessité accelerator Proton Beam Spallation Target
PDS-XADS Reference Accelerator Layout Strong R&D & construction programs for LINACs underway worldwide for many applications (Spallation Sources for Neutron Science, Radioactive Ions & Neutrino Beam Facilities, Irradiation Facilities)
Partitioning and Transmutation • Partitioning: • Separating out of spend fuel certain chemical elements • Transmutation: • Transforming a chemical element into another • Advanced fuel cycles with P/T may greatly benefit to deep geological storage: • Reduction of radiotoxicity. • Reduction of the heat load • larger amount of wastes can be stored in the same repository Meeting with WUT, Warsaw, 6 January 2009
FP-5 projects coordinated by ADOPT • TRANSMUTATION (6.5 MEuro) • Basic Studies: • MUSE • HINDAS • N-TOF_ND_ADS Projects on ADvanced Options for Partitioning and Transmutation (ADOPT) TRANSMUTATION (3.9 MEuro) Fuels: CONFIRM THORIUM CYCLE FUTURE PARTITIONING (5 MEuro) PYROREP PARTNEW CALIXPART TRANSMUTATION (6 MEuro) Preliminary Design Studies for an Experimental ADS: PDS-XADS TRANSMUTATION (7.2 MEuro) Technological Support: SPIRE TECLA MEGAPIE - TEST Meeting with WUT, Warsaw, 6 January 2009
From FP5 PDS-XADS to FP6 EUROTRANS Meeting with WUT, Warsaw, 6 January 2009
The EUROTRANS programme • EURopean research programme for the TRANSmutation of high level nuclear waste in an Accelerator Driven System • EU FP6 programme (2005-2009) • 31 research agencies & industries, 16 universities • Expands the EU FP5 project PDS-XADS (2001-2004) • 5 Domains (DM1=Design, ...) • Main GOAL of the EUROTRANS programme • Advanced design of a 50-100 MWth eXperimental facility demonstrating the technical feasibility of Transmutation on an ADS (XT-ADS, short-term realisation) • Generic conceptual design (several 100 MWth) of a European Facility for Industrial Transmutation (EFIT, long-term realisation) Meeting with WUT, Warsaw, 6 January 2009
Generation IV International Forum (GIF) Canada Japan Argentina Brazil France S. Africa Korea Switzerland UK US Euratom Generation IV International Forum Meeting with WUT, Warsaw, 6 January 2009
Interests of participating countries for GEN IV Systems VHTR GFR SFR LFR SCWR MSR GFR = Gas-Cooled Fast Reactor LFR = Lead-Cooled Fast Reactor MSR = Molten Salt Reactor SFR = Sodium-Cooled Fast Reactor SCWR = Supercritical Water-Cooled Reactor VHTR = Very-High-Temperature Reactor July 2005 leading role Meeting with WUT, Warsaw, 6 January 2009
Very-High-Temperature Reactor (VHTR) • Characteristics • Helium coolant • 900-950°C outlet temp • Water-cracking cycle • Benefits • Hydrogen production • High degree of passive safety • High thermal efficiency • Process heat applications Meeting with WUT, Warsaw, 6 January 2009
Supercritical-Water-Cooled Reactor (SCWR) • Characteristics • Water coolant at supercritical conditions • 550°C outlet temperature • 1700 MWe • Simplified balance of plant • Benefits • Efficiency near 45% with excellent economics Meeting with WUT, Warsaw, 6 January 2009
Gas-Cooled Fast Reactor (GFR) • Characteristics • Helium coolant • 850°C outlet temperature • Direct gas-turbine cycle • 600 MWth/288 MWe • Benefits • Waste minimization and efficient use of uranium resources Meeting with WUT, Warsaw, 6 January 2009
Lead-Cooled Fast Reactor (LFR) • Characteristics • Pb or Pb/Bi coolant • 550°C to 800°C outlet temperature • 120–400 MWe • 15–30 year core life • Cartridge core for regional fuel processing • Benefits • Proliferation resistance of long-life cartridge core • Distributed electricity generation • Hydrogen production • High degree of passive safety Meeting with WUT, Warsaw, 6 January 2009
Sodium-Cooled Fast Reactor (SFR) • Characteristics • Sodium coolant • 550°C Outlet Temp • 600 to 1500 MWe • Metal fuel with pyroprocessing, or • MOX fuel with advanced aqueous processing • Benefits • Waste minimization and efficient use of uranium resources Remark • Revival of Superphénix Technology Energy Supply and Climate Change,Bad Honnef, Germany, May 26-29 2008
Molten Salt Reactor (MSR) • Characteristics • Fuel: liquid fluorides of Na, Zr, U and Pu • 700–800°C outlet temperature • 1000 MWe • Low pressure (<0.5 MPa) • Alternate Fuel • Thorium possible • Benefits • ‘Final burn’ transmutation • Avoids fuel development • Proliferation resistance through low fissile material inventory • Major personal comment: • Thorium fueled nuclear reactors do not need • to be accelerator-driven • unnecessary economic burden and technical • complication Meeting with WUT, Warsaw, 6 January 2009
LWR Once-through cycle Amount of Transuranics Recycling in Thermal reactors Burndown using fast spectrum burners LWR Generation IV Equilibrium Time Separations LWR LWR Separations Separations FR ADS ADS Scenario using ADS to support Generation-III (and even Gen-IV ! ) reactors (only certain countries e.g. US) 2020 2030 2040 2050 Figure: M. Capiello & G. Imel (ANL) (ICRS-10/RPS2004) Meeting with WUT, Warsaw, 6 January 2009
Conclusion • Phasing out of fossile fuel needs to e sustainable • Nuclear Power likely to increase by factor 2-5 worldwide • Waste from installed (Gen-3), present (Gen-3) can be adressed • by dedicated transmutation systems (ADS) • (fast) Gen-4 concepts "self-incinerate" their waste. • Gen-4 molten salt reactor with Thorium produces much less waste