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1 The ITER era : the 10 year roadmap for the French fusion programme E. Tsitrone 1 on behalf of IRFM and Tore Supra team 1 : CEA, IRFM, F Saint-Paul-lez-Durance, France Association EURATOM-CEA TORE SUPRA CEA / DSM / Institut de Recherche sur la Fusion par confinement Magnétique CEA-Cadarache, ST-PAUL-LEZ-DURANCE (France)
2 Horizon 2020 opens a new era for fusion : from plasma physics to energy production :: Pioneering studies tokamak configuration March 25th, 1957: Signature of the EURATOM treaty in Rome :: Maturity of of concepts & Scalings Laws H mode on on AUG AUG Decision to to build buildjet :: MW MW D-T D-T JET JET View of the ITER site (Cadarache, France) Decision to to build builditer :: The Fusion Energy Era of of magnetic fusion research Horizon 2020 ITER ITER thermonuclear plasmas Decision to to build builddemo
3 Context for fusion in Horizon 2020 Horizon 2020 Energy production DEMO Definition CDA EDA Int nego construction operation IFMIF ITER CDA EDA Int nego construction construction operation operation CH, JA, KO, (US?) DEMO JT60SA construction operation * : indicative planning only JET EP2 Mid scale operation operation Horizon 2020 is a time for : preparing ITER operation developing materials for DEMO (IFMIF) launching conceptual design activities for DEMO establishing international collaborations needed Adapting programme, facilities and staff : Fusion programme roadmap
4 The European fusion roadmap : High level objectives for Horizon 2020 Objective 1 Delivering the EU procurements for ITER and the Broader Approach Timely completion of ITER and the Broader Approach projects : delivery of the EU procurements within cost, schedule and technical specifications. Objective 2 Preparing ITER operation Develop operational scenarios ITER performance Ensure the rapid and efficient start-up of ITER operation Protect the EU investment in ITER (risk mitigation to avoid delay / cost increase) Objective 3 Training ITER Generation To ensure that Europe will have the human resources (operators, fusion scientists and engineers) to exploit ITER in an international and competitive environment. Objective 4 - Laying the Foundations for Fusion Power Plants To drive forward the significant technology developments required for the timely design and construction of the demonstration fusion power plants that will follow ITER Objective 5 Promote innovation and EU industry competitiveness To ensure long term EU competitiveness in fusion technology and boost industrial value creation from the fusion programme
5 Major scientific headlines of the Accompanying Programme Objective 2 Prepare ITER operation ITER performance : relevant scenario + active plasma control ITER safe operation (disruptions, dust / T inventory, high performance with metallic walls ) Predictive modelling of fusion performance Objective 3 Train ITER Generation Fusion scientists, engineers, operators Objective 4 - Lay the Foundations for Fusion Power Plants Input for DEMO scenarios, including exhaust schemes Materials for DEMO DEMO key technologies DEMO conceptual design Potential of stellarators for reactors A completed DEMO engineering design. Key Reactor Technology Prototypes Validated Burning Plasma Operating Scenarios at High Energy Gain Physics Technology Fully qualified plasma facing Robust divertor concept to handle and structural materials high heat fluxes from the plasma
6 IRFM : the main French institute for research on magnetic fusion Physics of of hot magnetized plasma : Experiment, modeling, first principle theory Technology of of key fusion systems Mission : develop nuclear fusion as a future energy source ITER Operation of of large scale fusion devices Lower Hyb. Power (MW) 1 min Flux consumption (Wb) Steady state operation : a major issue on the way to a future fusion reactor T e (0) (kev) Density (x10 19 m -2 ) T i (0) (kev) Neutron (x10 10 /s) Z eff 2 min 6 min 1 GJ injected/extracted on Tore Supra (>6 min pulses)
7 Scientific and technical objectives The IRFM strategy ST1: Participating in the realisation of ITER and the Broader Approach projects ST2: Preparing the operation of next generation devices ST3: physical understanding through experimental and first principle approaches ST4: Developing a capability for fusion reactor conceptual studies. Management Managing the the transition to to a fusion research focused on on ITER M1: Adapting organisation and manpower M2: Developing strong national, European and international networks and initiating close cooperation with industry M3: Securing the resources necessary to achieve IRFM aims. Fully in line with the EU fusion roadmap * =1/128 JT 60 SA * =1/512
8 ST1 : Participating in the realisation of ITER and BA projects DESIGN INTEGRATION DIAGNOSTICS ITER diag. port Virtual reality room Wide spectrum diag.with large operational impact, linked to other S/T expertises at IRFM: Plasma facing components monitoring (Vis./IR) Magnetic measurements Reflectometry PP11 sketch RADIO FREQUENCY HEATING Participate to ICRH launcher procurement (design, monitoring, testing), and keep R&D on LHCD active (China, India, Korea, USA ) CRYOMAGNETISM procurement of JT 60 SA toroidal coils involvement in ITER superconducting magnets operation PLASMA FACING COMPONENTS Actively cooled PFCs developped for Tore Supra. WEST project : qualification of ITER W divertor technology in Tore Supra JT 60SA TF coil
9 INTEGRATED MODELLING ST2 : Preparing the operation of the next generation devices Dedicate Tore Supra to ITER and JT60SA preparation No adequate preparation of future fusion experiments without relevant modeling Complex involved physics need integrated platforms Support to the European effort + CRONOS suite, used for Tore Supra and other devices worldwide. PLASMA ENGINEERING AND REAL TIME CONTROL Real Time Control and protection for Tore Supra JET and ITER Strong connection to integrated modeling Tokamak plasma preparation interface Integrated Simulation Editor Controller Control Toolbox Controller Tokamak Models (tokamak+plasma) European simulation platform Kepler workflow Diagnostics TITAN test bed hydraulic plant PLATFORMS AND TEST FACILITIES FOR ITER Tore Supra, already a test platform relevant for ITER, will enhance this specific feature : WEST project Considered : other important test beds, such as a ITER port plug
10 WEST : minimising risks for ITER operation Use Tore Supra assets to prepare ITER exploitation WEST Long pulse H mode :: ITER reference Circular configuration (limiter) X point configuration (divertor) WEST : filling the gap towards ITER actively cooled divertor First integrated test :: technology of of high heat flux W PFC + tokamak operation
11 WEST : extending H mode towards steady state and exploring PWI with actively cooled W Standard : long pulse 10 MW/m 2 High power : high performance shorter pulse High fluence : ITER fluence within a few days (6 years for JET!)c Open for collaboration : EU + China, US WEST : in time for ITER Inside WEST Test PFC
12 ST3 : physical understanding through experimental and first principle approaches FIRST PRINCIPLE SIMULATIONS High performance computers «numerical tokamak» Intensive collaborations (applied mathematics, computing science) development, validation, application : turbulent transport, ELMs, GYSELA JOREK SCIENTIFIC EXPLOITATION OF EXPERIMENTAL PLATFORMS Tore Supra heating upgrade completed : extend long pulse operational space Experimental validation of models + preparing WEST operation Participation to JET ITER like wall + W7-X, JT60SA JET Tore Supra W7-X JT60SA
13 ST4 : Developing a capability for fusion reactor conceptual studies Reactors studies : other CEA laboratories and integrated in the European effort System code Refocus on credibility: System code and systemic studies Strategic topics (resources, costs, ) Specific studies : divertor, blankets, materials (IFMIF) Summary IFMIF Main challenge for the fusion programme over the next decade : ITER IRFM strongly committed to making ITER a success Specific programme : WEST project Open to partners for contribution / joint exploitation Assets : integration physics / technology / operation steady state Promising synergies with Asian programmes + stellarators Consistent 10 years programme opens the way to a future reactor
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