The European fusion research programme aims at developing fusion as an energy source , i.e.

1. R&D priorities for the fusion programmeand contributions from EFDAon behalf of J. Pamela, EFDA LeaderPresented by B. WeyssowEFDA ROH&CD and FuellingTransportRemarks, comments, requests: boris.weyssow@efda.com

2. The European fusion research programme aims at developing fusion as an energy source, i.e. developing the knowledge in physics, technology and engineering required to design and build fusion power plants. => power plant-oriented strategy => key steps in this strategy: ITER and DEMO => ‘Fast Track’ approach: DEMO = single step after ITER IFMIF (materials test facility) operating in parallel to ITER

3. Strategy towards DEMO and Power Plants TECHNOLOGY PROGRAMME ITER DEMO POWER PLANT PHYSICS PROGRAMME Alternative Concepts (Stellarator)

4. Gap Analysis presented to the Facilities Review (2008) DEMO Phase 1 and phase 2: different sets of blankets 4

5. What we expect from ITER • The scientific demonstration of fusion: a Burning Plasma at Q=10 • Development of long pulse/steady state modes of plasma operation (with a target of power amplification Q=5) • Functional tests and test under neutrons of Test Blanket Modules (tritium breeding) • Demonstration of a number of key components close to power plant requirements (magnets, vessel, T plant, safety, etc) • a key input to support the launch of DEMO construction in about 20-25 years • a necessary input, which however needs to be complemented by a significant accompanying programme in technology and physics

6. CORE PROGRAMME (1/2) As recommended by the Facilities Review Panel (October 2008) During the period of ITER construction the key strategic R&D emphasis should be on A1) Supporting ITER construction and preparation for operation • Design and construction of ITER systems and components • Resolving ITER physics issues which might limit the performance, constrain the accessible parameter space and/or impact on the operational reliability; • Preparing rapid start-up of ITER targeting promising operational regimes; • Strengthening diagnostic and modelling capabilities and fostering developments for improved solutions. A2) Preparing DEMO design, simultaneously carrying out long lead R&D by • Strengthening the materials research programme for DEMO and future fusion power plants and establishing experimental means for validation; • Advancing Tokamak and Stellarator concepts for optimizing the path towards DEMO and a commercial fusion power plant; • Establishing a DEMO groupfor proceeding towards the definition of a conceptual DEMO design, steering the DEMO R&D programme and preparing industrial involvement.

7. CORE PROGRAMME (2/2) As recommended by the Facilities Review Panel (October 2008) During the following decade the focus must shift towards B) Preparing for DEMO construction, based on ITER and the accompanying R&D, with increased involvement of industry and utilities, by focusing on • Achieving the goals of ITER in DEMO relevant conditions with emphasis on steady-state aspects; • Developing a blanket and auxiliary systems compliant with DEMO conditions; • Optimising and validating suitable materials and components for DEMO; • Assessing concept improvements for the Tokamak and the potential of the Stellarator for optimizing the path towards commercial fusion power; • Developing a “numerical burning plasma device” for the detailed prediction of fusion performance and assistance in the definition and design of DEMO; • Establishing the engineering design for DEMO. These ITER and DEMO priorities must be complemented by C) Pursuing innovation D) Maintaining and renewing the staffing basis of the Programme

8. R&D in support to ITER

9. Technology R&D in relation to ITER Activities in direct support to construction (qualification of techniques, prototypes): magnets (including cold tests), vacuum-vessel, blankets, divertor, T-plant etc. R&D in laboratories will be needed short & mid-term =activities linked to construction long term = activities linked to the ITER experimental programme • Plasma Facing Elements (First Wall: Be short term; Divertor: W mid-term) • Dust and Tritium removal technologies (mid-term) • Fuelling and pumping technologies (mid-term) • In-vessel coils (mid-term) • Tritium Breeding Blanket (mid and longer-term): • Preparation of Test Blanket Modules (structural and functional materials, Tritium extraction technique, joining and other manufacturing technologies) • Tritium Plant (mid-term) • Remote handling (mid-term) • Heating and current drive techniques (mid and longer-term) • Neutral beam sources and accelerators • Gyrotrons (possibly 2 MW units) • Lower hybrid couplers (test of ITER-relevant coupler on tokamak)

10. Physics R&D in support of ITER(support to construction and preparation of operation) - Preparation for burning plasma experiments • Fast particle physics • Burn control • Diagnostics for burning plasma • Minimisation of fuel retention • Plasma wall interaction (Physics of erosion, codeposition, T-retention in W and Be) • Diagnostic techniques (T-retention, Dust etc.) • Control of MHD • Plasma performance: NTMs, RWMs • Limitation of transient heat loads: ELMs (among the highest priorities) • Reliable operation: Disruption avoidance and mitigation

11. Physics R&D in relation to ITER • Optimisation of plasma operation with metallic plasma facing materials (full W divertor) • Development of plasma scenarios for long pulse / steady state • Current Drive physics • Improved H-mode • Advanced modes with extensive current profile control • Transport and Confinement Physics • H-mode and Edge Pedestal • Turbulent transport • Integrated Modelling • Progress on first principles physics codes / validation against experiments • Common framework and tools for integrated modelling (interpretative and predictive)

12. Physics from ITER to DEMO • Fully validated ‘tokamak simulator’ • Very robust plasma scenarios, compatible with control capabilities (limited set of diagnostics and actuators; balance between performance and reliability) • Highly radiative plasma scenarios • Very long pulse operation

13. EFDA Contribution

14. EFDA All EU Laboratories/Institutions working on Fusion are parties to EFDA • Collective use of JET • Reinforced coordination of physics and technology in EU laboratories • Training • EU contributions to international collaborations outside F4E

15. JETPresented by Dr. RomanelliEFDA Associate Leader

16. Coordination of R&D in Associations: EFDA Task Forces & Topical Groups First Call for Participation EFDA WP2010 TG HCD, Diag, MHD, Transport now closed

17. Coordination of R&D in Associations: EFDA Task Forces & Topical Groups Task Forces under EFDA PWI Task Force: Leaders E.Tsitrone (CEA) and R.Neu (IPP) ITM Task Force: Leaders P.Strand (VR), R. Coelho (IST), LG Eriksson (EC), G.Falchetto (CEA) Topical Groups under EFDA Materials Topical Group: Chairmen S.Dudarev (UKAEA) M. Reith (FZK) Transport Topical Group: Chairman C.Hidalgo (CIEMAT) H&CD Topical Group: Chairman A.Becoulet (CEA) Diagnostics Topical Group: Chairman T.Donné (FOM) MHD Topical Group: Chairman P.Martin (ENEA-RFX)

18. Exemple of coordinated activity: Task WP08-HCD-03-01Midterm Progress Coordinator: Tuong Hoang For: J.F. Artaud, A. Bécoulet, J.H. Belo, G. Berger-By, J.M. Bernard, Ph. Cara, A. Cardinali, C. Castaldo, S. Ceccuzzi, R. Cesario, J. Decker, L. Delpech, A. Ekedahl, J.Garcia, P. Garibaldi, G. Giruzzi, M. Goniche, D. Guilhem, J. Hillairet, G. T. Hoang, J. Hua, Q.Y. Huang, F. Imbeaux, F. Kazarian, S.H. Kim, X. Litaudon, R. Maggiora, R. Magne, L. Marfisi, S. Meschino, D. Milenasio, F. Mirizzi, L. Pajewski, L. Panaccione, Y. Peysson, G. Schettini, P.K. Sharma, M. Schneider, A. Tuccillo, O. Tudisco, G. Vecchi, S. R. Vilari, K. Vulliez

19. LH PROGRAM IN RUN UNDER EFDA • TASK WP08-HCD-03-01 ‘LH4IT’,following the ITER STAC recommendation • Providing a pre-design document including the conceptual design, costing, possible procurement allocation, WBS, R&D needs • CEA, ENEA, IST, POLITO, Univ. ROME 3 (> 4ppys) Collaboration with IO- HCD Department (Integration aspect) and the International Fusion community: China, India, Korea, US and Japan (follow-up only) • Training program LITE (7 trainees): 4 trainees on LH Focusing on RF/mechanical aspects of the IC and LH systems (whole system, from the source to the antenna) • Validation of PAM concept at Tore Supra with EU and non EU partners

20. ITER LH System: WBS • Working groups • Physics • Launcher • T-lines • Power Supply • Control & Protection Diagnostics • Integration LITE Physics design Launcher conceptual design Transmission lines Integration Done or on-going

21. ITER LH System: Physics Modeling LH current and deposition vs N// Scenario 4 Propagating region for N//= 2 What has been done? • Optimize the N// range by performing integrated simulations of propagation / absorption in ITER various design scenarios (SS, Hybrid, ramp-up phase and baseline) in varying ne, Te, and poloidal position • Choice of location in ITER to avoid magnetic connection (coupling issue) • Alpha absorption issue

22. ITER LH System: Launcher What has been done? • Retrieve results of DDD2001 (with various codes). Update the heat fluxes • Modify the DDD2001 design to • Improve the N// flexibility, power density, • Optimize the directivity, RF hardware (phase shifters, bi-junction) • Thermo-mechanical analysis.Study different options for the Be front face • Initiate the design of a Fully Active MJ for a back-up solution (RF design, thermal analysis) Optimizing bi-junctions DDD2001

23. Antenna Front Face 4 different models have been studied: - DDD2001 PAM model - 2 Alternative PAM models “Case A” and “Case B” - FAM, alternative concept to the PAM DDD2001 Case B FAM Case A

24. Port # 11 Klystrons ITER LH System: Transmission-lines 48 RF Windows What has been done? • Revise the DDD2001 strongly Reduce the number of TLs (klystron 1MW in DDD2001; 500kW now) • Integration in ITER environment • Design of RF windows (on-going)

25. ITER LH System: Power Supply & Control & Protection • What has been done? • Characterize Power Supply requirements and conceptual design (HVDC PS based on PSM, pulse step modulator, technology) • Characterize specific diagnostics • RF measurements: Power and phase control and safety interlocks • Window arc detection: Optical fibers compatible with ITER environment • Density measurement at grill mouth: Front face reflectometer • Diagnostic viewing the antenna front for detecting arcs: IR/VIS cameras, bolometry. Location of diagnostics with respect to the LH antenna

26. EFDA 2010 Work Programme / Overview => Longer term vision => Focus along the seven R&D Missions proposed by EFDA and endorsed by the Facilities Review Panel • Burning Plasmas • Reliable Tokamak Operation • First wall materials & compatibility with ITER/DEMO relevant plasmas • Technology and physics of Long Pulse & Steady State • Predicting fusion performance • Materials and Components for Nuclear Operation • DEMO Integrated Design: towards high availability and efficient electricity production. The programme priorities take into account the ITER research plan, activities conducted under F4E and the outcome of ITPA

27. Mission I Burning Plasmas Priority support is directed to the measurements of fusion products and related diagnostics Confined alphas measurements Lost alphas measurements Neutronics RISO Design of neutron spectrometer (ENEA) Fuel ion ratio TEXTOR (FZJ) Diagnostics hardware for improved measurements of confined and lost alphas, neutrons and fuel ion ratio in support of diagnostic developments for ITER and physics studies in present machines and for co-ordinated experiments.

28. Mission II Reliable Tokamak Operation Priority support is focused on Disruptions studies and ELM mitigation, with a specific emphasis on high-Z materials for the Plasma Wall interaction aspects, and on Dust & Tritium emerging technologies for possible application on ITER. Radiation during Mass Gas Injection (CRPP) MAST : filaments (UKAEA) Specific software developments for linear/non-linear MHD studies including 3D geometry and kinetic effects. Co-ordinated experiments on mitigation and control of MHD instabilities. Diagnostics for improved measurements of runway electron beam and impurity dynamics, halo currents and vessel forces.

29. LH  ICRH : fast e- Mission III First wall materials & compatibility with ITER/DEMO relevant plasmas Priority support on the development of thermography for metallic walls, a key issue for JET and ITER. JET Tore Supra (CEA) Diagnostics hardware for development of Thermography for Metallic Walls and co-ordinated experiments on mitigation and control of heat loads.

30. Mission IV Technology and physics of Long Pulse & Steady State (I) General H&CD and Fuelling physics and Technology: Cadarache8-11 february 2010 • EU contribution to the LHCD for ITER development plan: coordination; diagnostics, conceptual design; source, transmission lines and antenna. • Developments Neutral Beam Advanced Technologies: co-ordination, conceptual designs and modelling of sources, accelerator techniques and alternative neutraliser technology. • NB-CC meeting: Garching 24-26 november 2009 • - Fast wave off-axis current drive physics, antenna modelling, power sources and co-ordination. LHCD Antenna (CEA)

31. Mission IV Technology and physics of Long Pulse & Steady State (II) Priority support for the development of new diagnostic concepts and analysis techniques, including further development of plasma position control in long pulse operation. • Development of plasma position control in long pulse operation; implementation and tests in present machines. • Development of new diagnostic concepts and analysis techniques, implementation and tests in present machines. • Development of data analysis, validation, calibration and real time techniques; implementation and tests in present machines. • Co-ordinated experiments. non-magnetic plasma position diagnostic (ENEA)

32. Mission V pressure H-mode pedestal L-mode distance from axis Predicting fusion performance (I) Priority support focused on detailed studies of the L-H transition and plasma pedestal properties, including the development of better diagnostics; and on electron transport studies (dominant electron heating as on ITER). • Diagnostics hardware for improved measurements of key parameters related to L-H transition (Edge Currents, Flows, Neutral densities and Turbulence) in support of detailed physics studies. • Diagnostics hardware for improved measurements of key parameters related to electron transport, impurity transport, plasma rotation and edge turbulence in support of detailed physics studies • Co-ordinated experiments.

33. Mission V Result to database EFIT equilibrium Initialisation Refined HELENA equilibrium MISHKA linear MHD stability Predicting fusion performance (II) Integrated Tokamak Modelling, priority support is focused on coordination activities,standardization towards joint tools, structures and formats, and the ETS. ITM Workflow in Kepler ITM Gateway in Portici (ENEA) • Incorporation of new modules and promoting their use in advanced applications. • Developments towards platform enhancements while maintaining a robust production level platform (ISIP) • Continuing development of the ETS with additional modules being incorporated, as well as V&V efforts of these modules.

34. HPC-FFHigh Performance Computer for Fusion Applications • Located in the Jülich Supercomputing Centre • 1080 computer nodes: • Bull NovaScale R422-E2 • 20 racks with 54 nodes each • Processor: Intel Xeon X5570 (Nehalem-EP) quad-core, • 2.93 GHz • Memory: ~250 TB • Peak theoretical performance: ~ 100 TFlop/s • Operating since 5 August 2009

35. Mission VI Materials and Components for Nuclear Operation (I) Development of ground-breaking advanced tools for Radiation Effects Modelling and Experimental Validation in EUROFER as 1st Priority Displaced atoms (green) and vacant lattice sites (red) at the end of the collision phase of displacement cascades created by 5, 10 and 20keV atomic recoils at 600K (UKAEA).

36. Mission VI Materials and Components for Nuclear Operation (II) Optimise the conditions for Nano-Structuring Oxide dispersion strengthened(ODS) Ferritic Steels: fabrication at the semi-industrial scale and characterisation ODS Should Mitigate Inter-granular Embrittlement and Swelling

37. Mission VI Increase of Fracture Toughness W WL10 W26Re Annealing 1 hour 835 0C Initial Microstructure Non-Affected Loss of FractureToughness 1200 0C Unacceptable Recrystallisation Materials and Components for Nuclear Operation (III) Develop Heat Resistant and Oxidation Resistant W-alloys: Priority Support focused on Fabrication of new alloys and their joint characterisation

38. Other/new coordinated activities Fuelling (physics & Technology) • Gas flow in divertor; pumping rate influence on scenarios; pellet fuelling database; divertor operation • Tech: New concepts for cryopumps; high speed pellet injection; concepts for fuelling system. DEMO (Physics and Technology) • Physics: Stability margins, H&CD for DEMO, radiation • Superconductors for fusion applications: aim at demonstration coils in 3 years (MgB2) / 6 years (YBCO)

39. in 2100 inWEU CO2 (ppm) Socio-Economic Research on Fusion (SERF) • Launched in 1997 • Objectives revised in 2008 following recommendations of an EFDA ad hoc group • Multi-disciplinary field, complementing existing knowledge bases • Economical viability, social acceptability, societal implications of fusion power • Major research lines: • Fusion economics: direct, indirect and external costs of fusion • Fusion in the energy system  long-term energy scenarios • Fusion as a large technical and complex system • Public opinion, awareness and acceptance of fusion  communication strategy CO2 (ppm)

40. Public Information • Fusion Expo • EFDA Newsletter • European Public Information Group • PI materials • visits at JET • Participation in Eiroforum

41. TRAINING UNDER EFDA Goal Oriented Training Programme Fusion Fellowships Programme - up to 10 post-docs per year selected among proposals from Associations - fellowships awarded according to the sole quality of the applicants and their proposals => develop a brand of excellence

42. Summary