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Fusion Research new horizons

Fusion Research new horizons. Jerome Pamela EFDA Leader. Content of the talk Fusion strategy ITER: a major Step Accompanying programme IFMIF and Materials R&D Organisation of the European programme Involvement of the Portuguese Association. Structural Materials And T breeding. TBM.

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Fusion Research new horizons

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  1. Fusion Researchnew horizons Jerome Pamela EFDA Leader Jerome Pamela Lisbon, 24 July 2007

  2. Content of the talk Fusion strategy ITER: a major Step Accompanying programme IFMIF and Materials R&D Organisation of the European programme Involvement of the Portuguese Association Jerome Pamela Lisbon, 24 July 2007

  3. Structural Materials And T breeding TBM IFMIF • Components • SC Magnets • Tritium Handling System • Plasma Facing Compts. • Remote Mainten. System • Heating System • Safety • Test Blanket Modules ITER • Facilities for Plasma R&D • Confinement • Impurity Control • Plasma Stability • ITER/DEMO Physics Support towards DEMO DEMO JET JT60SA Jerome Pamela Lisbon, 24 July 2007

  4. Structural Materials And T breeding TBM IFMIF • Components • SC Magnets • Tritium Handling System • Plasma Facing Compts. • Remote Mainten. System • Heating System • Safety • Test Blanket Modules ITER • Facilities for Plasma R&D • Confinement • Impurity Control • Plasma Stability • ITER/DEMO Physics Support Towards DEMO DEMO JET JT60SA Jerome Pamela Lisbon, 24 July 2007

  5. ITER: a major stepTokamak: a success story • Progress in fusion can be compared with the computing power and particle physics accelerator energy • Present machines produced significant DT fusion power TFTR (US) 10MW in 1994 and JET(EU) 16MW in 1997 • A further step by a factor 5-6 in performance (n T t) to get to the reactor domain NEXT STEP NEEDED ITER Jerome Pamela Lisbon, 24 July 2007

  6. Central Solenoid Nb3Sn, 6 modules Cryostat 24 m high x 28 m dia. Toroidal Field Coil Nb3Sn, 18, wedged Vacuum Vessel 9 sectors Blanket 440 modules Poloidal Field Coil Nb-Ti, 6 Port Plug heating/current drive, test blankets limiters/RH diagnostics Torus Cryopumps, 8 Divertor 54 cassettes The core of ITER 5,3 T on plasma axis Major plasma radius 6.2 m Plasma Volume: 840 m3 Plasma Current: 15 MA Typical Density: 1020 m-3 Typical Temperature: 20 keV Fusion Power: 500 MW Machine mass: 23350 t (cryostat + VV + magnets) Jerome Pamela Lisbon, 24 July 2007

  7. ITER: a major StepScientific objective: the first burning plasma on earth A burning plasma is dominated and maintained by its own internal heat source from the DT reactions => characterized by the • power amplification factor: Q • Q = power generated by fusion reactions / heating power • injected in the plasma • fractionof plasma self-heating by fusion borna-particles: • fa = Q/(Q+5) With a power amplification Q > 10, ITER will provide for the first time access to self-heated plasmas (fa > 2/3) and provide the ultimate scientific demonstration needed Jerome Pamela Lisbon, 24 July 2007

  8. CS conductor (Incoloy jacket) ITER: a major StepCoils of unprecedented size and performance Jerome Pamela Lisbon, 24 July 2007

  9. ITER: a major StepDemanding High Heat Flux Components • HIGH HEAT FLUX COMPONENTS • FOSSILE FIRED BOILER WALL (ABB) • FISSION REACTOR (PWR) CORE • ITER DIVERTOR DESIGN • HEAT FLUX • average MW/m2 • - maximum MW/m2 • 0.2 • 0.3 • 0.7 • 1.5 • 3 – 5 • 10 – 20 Max heat load MJ/m2 Lifetime years Nr. of full load cycles Neutron damage dpa Structure material - 25 8000 - Ferritic-Martens. steel - 4 10 10 Zircaloy - 4 10 3 3000 0.2 CuCrZr & CFC/W • Coolant • - pressure MPa • - temperature °C • - velocity m/s • - leak rate g/s • Water-Steam • 28 • 280-600 • 3 • <50 • Water • 15 • 285-325 • 5 • <50(SG) • Water • 4 • 100 – 150 • 9 – 11 • <10-7 Irradiation Tests atPetten Jerome Pamela Lisbon, 24 July 2007

  10. Diagnostic access Diagnostic access EU-supplies several ITER diagnostics Jerome Pamela Lisbon, 24 July 2007

  11. ITER - Diagnostics Lidar Polari-meter Jerome Pamela Lisbon, 24 July 2007

  12. ITER: An unprecedented international collaboration Jerome Pamela Lisbon, 24 July 2007

  13. Structural Materials And T breeding TBM IFMIF • Components • SC Magnets • Tritium Handling System • Plasma Facing Compts. • Remote Mainten. System • Heating System • Safety • Test Blanket Modules ITER • Facilities for Plasma R&D • Confinement • Impurity Control • Plasma Stability • ITER/DEMO Physics Support A programme towards Fusion Energy:Accompanying Programme DEMO JET JT60SA Jerome Pamela Lisbon, 24 July 2007

  14. Strong Accompanying Programme in physics in parallel to ITER construction Includes satellite tokamaks (JET and then JT60SA) See later description of EFDA for other activities Jerome Pamela Lisbon, 24 July 2007

  15. JET is the largest and most successful Tokamak On the path to ITER The ITER design is based largely on the success of JET JET 6 meters 80 m3 16 MW ASDEX Upgrade 3.3 meters 14 m3 ITER 12 meters 800 m3 500 MWth Diameter (plasma) Plasma Volume DT Fusion power (world record) Jerome Pamela Lisbon, 24 July 2007

  16. Several outstanding ITER-relevant technologies were / are being developed at JET Routine performance of in-vessel remote handling tasks => JET: contributing to ITER technologies Jerome Pamela Lisbon, 24 July 2007

  17. JET is collectively used by EFDA Associates More than 300 scientists from all over Europe work on this unique facility during the 2006-2007 Campaigns Jerome Pamela Lisbon, 24 July 2007

  18. DT integrated experiment Burning Plasma Physics Confirmation of reduced T-retention DT test of fully wall-compatible scenarios (e.g. isotopic effects) ITER-like wall experiment Plasma scenarios in ITER configuration Plasma scenario compatibility JET longer term programme: developing fully integrated plasma scenarios for ITER Jerome Pamela Lisbon, 24 July 2007

  19. Required Enhancements DT integrated experiment • Heating Power Upgrade • Plasma control upgrade • Diagnostics & Real Time Control • ITER-like wall • Wall diagnostics • Detritiation techniques Confirmation of reduced T-retention DT test of fully wall-compatible scenarios ITER-like wall experiment Plasma scenarios in ITER configuration Plasma scenario compatibility • Pellet injector (ELM pacing) • RMP (ELM mitigation) Jerome Pamela Lisbon, 24 July 2007

  20. EP2 scope has been confirmed during 2006 (>60M€ investment cost) New ITER-Like Wall Enhancement of Neutral Beam Capabilities (NBE) High Frequency Pellet Injector (HFPI) Plasma Control Upgrade 18 Diagnostic Projects Shutdown foreseen to start in November 2008 Scientific exploitation 2010 and possibly beyond JET Enhancement Programme 2: EP2 Jerome Pamela Lisbon, 24 July 2007

  21. JET ITER-like wall experiment • 700m2 Beryllium first wall • low Z • Oxygen getter • Optimise plasma performance • But large erosion & melting ITER • 100m2 Tungsten • Low erosion • high melting T • Negligible T retention • Optimise lifetime & T- retention • But high Z & melting W JET • 50 m2 Graphite CFC • Lowish Z • No melting in transients • Superior heat shock behaviour • Optimise heat flux resistance • But large erosion & T retention CFC Jerome Pamela Lisbon, 24 July 2007

  22. 20 s pulse length limit EP2: Neutral beam UpgradeNB Power increase from 25 to 34 MWPulse length from 10 to 20 sPlasma scenarios will be developed closer to ITER conditions Jerome Pamela Lisbon, 24 July 2007

  23. JT-60SA (in the frame of the Broader Approach between EU & Japan) as a satellite to ITER (support to ITER during ITER operation) • Enhanced flexibility in aspect ratio (A=2.6-3.1) and plasma shape. • High power heating/current-drive system, 41MW for 100 s, will be prepared. • High beta steady-state operation (N~4, fBS~70%) for DEMO and high density ELMy H-mode operation (ne~9x1019m-3) for ITER are planned. Jerome Pamela Lisbon, 24 July 2007

  24. Structural Materials And T breeding TBM IFMIF • Components • SC Magnets • Tritium Handling System • Plasma Facing Compts. • Remote Mainten. System • Heating System • Safety • Test Blanket Modules ITER • Facilities for Plasma R&D • Confinement • Impurity Control • Plasma Stability • ITER/DEMO Physics Support A programme towards Fusion Energy: IFMIF and Materials R&D DEMO JET JT60SA Jerome Pamela Lisbon, 24 July 2007

  25. Materials R&DPotential for limited long-lived radwaste (Moeslang)- Requires low activation material- Eurofer already shows good prospect Jerome Pamela Lisbon, 24 July 2007

  26. IFMIF Protonspallation 400 He generation(appm/year) Fusion 200 ITER Fission 0 0 20 40 Displacement damage (dpa/year) IFMIF and Materials Activation by fusion neutrons: a specific problem 14 MeV neutrons from DT reactions: He generation rate higher than from slower neutrons => swelling Requires a specific facility (IFMIF) Jerome Pamela Lisbon, 24 July 2007

  27. PIE Facilities Test Modules InsideTest Cell Ion Source RFQ High-Energy BeamTransport Li Target 0 20 40 m Li Loop IFMIF and Materials International Fusion Materials Irradiation Facility Engineering, Validation and Design Activities starting in the frame of the EU-Japan Broader Approach Overview of the IFMIF design with major subsystems (Moeslang) Jerome Pamela Lisbon, 24 July 2007

  28. The Three Major IFMIF Components Accelerator Target Test Cell Deuteron accelerators: 40 MeV 250 mA(10 MW) • 10 MW beam heat removal with high speed liquid Li flow • Irrad. Volume ~ 0.5Lfor 1014 n/(s･cm2), (≥20 dpa/year) • Temperature: 250<T<1000℃ Li flow neutrons Test pieces HEBT LEBT D+ d-beams Two accelerators n-irradiation (~1017 n/s) Heat exchanger ECR source RFQ DTL PIE Typical reactions: 7Li(d,2n)7Be, 6Li(d,n)7Be, 6Li(n,T)4He ECR source:155 mA, 95 keV Two 175 MHz Accelerators: each 125 mA and 40 MeV, acceleration by Radio Frequency Quadrupoles (RFQ) and Drift Tube Linacs (DTL) Footprint on target: 20cm wide x 5cm high (1 GW/m2) EM pump Total Availability: 70% Jerome Pamela Lisbon, 24 July 2007

  29. Content of the talk Fusion strategy ITER: a major Step Accompanying programme IFMIF and Materials R&D Organisation of the European programme Involvement of the Portuguese Association Jerome Pamela Lisbon, 24 July 2007

  30. Joint Undertaking for ITER (F4E) Domestic Agency to provide and manage EU contribution to ITER Contribution to Broader Approach located in Spain (Barcelona) Chairman C.Varandas New Organisation in Europe from 2007 European Fusion Development Agreement (EFDA) • Agreement between all EU fusion labs and Euratom • Coordinated activities (physics in support to ITER, longer term technology) European Laboratories (associated to Euratom) Jerome Pamela Lisbon, 24 July 2007

  31. BROADER APPROACH • Bilateral agreement between the Government of Japan and EURATOM. • three projects: • IFMIF/EVEDA: Engineering Validation and Engineering Design Activities for the International Fusion Materials Irradiation Facility • The Satellite Tokamak Programme (JT-60-SA): upgrade of JT60U • IFERC The International Fusion Energy Research Centre : Computer Simulation Center, DEMO Design and R&D Coordination Center, ITER Remote Experimentation Center • Mainly contribution in kind. European contribution from France, Italy, Spain, Germany and Switzerland. Belgium under discussion. • The Broader Approach will last 10 years • Allocation of Contribution of the Parties 678 M€ (50% JS, 50% EU) Jerome Pamela Lisbon, 24 July 2007

  32. 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 Jerome Pamela Lisbon, 24 July 2007

  33. EFDA Two Programmatic Objectives in the Workplan to prepare for the operation and exploitation of ITER; to further develop and consolidate the knowledge base needed for overall fusion development and in particular for DEMO. The achievement of these objectives shall keep the European Fusion community in a frontline position in preparation of the experimentation on ITER. Jerome Pamela Lisbon, 24 July 2007

  34. EFDA Outline of the work five programmatic Pilars: 1- development of plasma scenarios for ITER and DEMO, 2- plasma wall interaction and plasma facing materials, 3- theory & integrated modelling, 4- Emerging Fusion Technologies and Plasma Engineering Techniques, 5- Fusion as a future energy source (includes Public Information, Socio-Economics etc.). Jerome Pamela Lisbon, 24 July 2007

  35. EFDA Activities in pursuit of the EFDA objectives I- Co-ordinated activities of the Associations for research, and for the development and exploitation of common tools or facilities/devices; II- Collective use of the JET facilities III- Training and carrier developmentof researchers, promoting links to universities and carrying out support actions for the benefit of the fusion programme IV- Providing a framework for coordinating European contributions to international collaborations In all the EFDA activities, specific effort will be devoted to integrate the new Member States/Associations into the EFDA programme. Jerome Pamela Lisbon, 24 July 2007

  36. EFDA Co-ordinated activities of the Associations for research, and for the development and exploitation of common tools or facilities/devices; joint scientific exploitation of major fusion devices, that will be promoted, in view of achieving the objectives of the EFDA Workplan, and encouraged by the provision of appropriate incentives and framework; the co-ordination of common tools developed under the EFDA Workprogrammes; the co-ordination of R&D activities requested by the Joint Undertaking “Fusion for Energy”, which might include physics R&D conducted in Associations and/or under international collaboration; the development of quality assurance standards and procedures, remote participation tools, common engineering modelling tools and standards, etc. in the Associations; the coordination of relevant data bases. The activities will be carried out in pursuance of the EFDA programmatic objectives and in view of an efficient participation of the Associations in ITER construction and exploitation and in preparation of DEMO. Task Forces and Topical Groups will be set up as needed to support the EFDA Leadership in the implementation of these actions. EFDA will also be in charge of identifying the need for urgent development of facilities in support of the objectives of the Workplan and of recommending on resource allocation. Jerome Pamela Lisbon, 24 July 2007

  37. Training a new generation of physicists and engineers:- 200 staff to be trained over the coming 5 years under “training projects”- new Fusion research grants: competition will be open to all post-docs in European Labs / ~10 grants per year Jerome Pamela Lisbon, 24 July 2007

  38. Content of the talk Fusion strategy ITER: a major Step Accompanying programme IFMIF and Materials R&D Organisation of the European programme Involvement of the Portuguese Association Jerome Pamela Lisbon, 24 July 2007

  39. Participation of IST staff in EFDA JET Work Programme 2006 IST Jerome Pamela Lisbon, 24 July 2007

  40. IST staff involved in the EFDA JET Work Programme 2006 Jerome Pamela Lisbon, 24 July 2007

  41. Fast ion losses associated with MHD modes Resonance Condition for Alfvén Cascades Excitation X-mode versus O-mode Interferometry/reflectometry measurements of Alfvén Eigenmodes with strong reversed shear AE excitation with ICRH beatwaves Neural network studies to forecast the occurrence of disruptions and ELMs Study of the toroidal plasma rotation braking induced by error-fields Giant sawtooth stability and core-localized fluctuations in JET plasmas Using MHD as a diagnostic for rotation The role of double tearing activity in the current density rearrangement scheme in extreme reversed shear JET plasmas MSE analysis Characterization of the non-thermal properties of the Electron Cyclotron Emission registered during ELMs in high performance plasmas Modelling of Advanced Tokamak Scenarios Modelling impurity transport Exploration of beam modulation as a tool for viscosity and heat transport measurements Determination of plasma rotation in JET discharges with low momentum input Quasi Double Null identify experiments for JET and AUG Power exhaust studies in MKII-HD ELMy H modes Tritium recovery and runaway suppression with gas terminations in high current plasmas Mitigation of disruptions – DMV Commissioning of new/upgraded diagnostics/systems Main areas of involvement Jerome Pamela Lisbon, 24 July 2007

  42. Some Highlights Jerome Pamela Lisbon, 24 July 2007

  43. Scenario with tolerable ELMs in JET (1) Quasi Double Null identify experiments for JET and AUG (I. Nunes) AUG JET JET shape scaled to match as much as possible the AUG one JET parameters: Ip = 0.86 MA, BT = 1.1 T, ne,ped = 2.5x1019 m-3, Te,ped = 0.6 Kev Jerome Pamela Lisbon, 24 July 2007

  44. Study of Type II ELM regime as an alternative for ITER with acceptable ELM size Steady state regime with Type II ELMs obtained with 5% temperature drop, H98(y,2)≈ 0.9 Necessity of quasi double null configuration confirmed Type II ELMs also observed at Ip = 1.2 and 1.6 MA (reduced ν*) However, density scans show that operational space for Type II ELMs at Ip valuesabove is narrow, ne,ped/nG≈ 0.7 - 0.8, and lowest ν*≈ 0.3 Operational space of Type II ELMs (I. Nunes) Scenario with tolerable ELMs in JET (2) Jerome Pamela Lisbon, 24 July 2007

  45. X-mode reflectometry measurements of Alfvén Eigenmodes First ever simultaneous measurement of radial location and time-frequency of Alfvén Cascades (S. Hacquin) At t  6.5 sACs appearing on 85 GHz channel but disappearing on 92 GHz channel => RAC 3.3 m Before t  6.5 sTAEs mainly on 85 GHz => RTAE 3.35 m TAEs • Spatial and temporal evolution of qmin(R,t) obtainable • Important for the development of advanced scenarios ACs ACs Jerome Pamela Lisbon, 24 July 2007

  46. Both co- and counter-rotating profiles are observed in RF heated plasmas Ohmic Plasmas are counter-rotating NBI plasmas are co-rotating Toroidal rotation in Ohmic and RF heated plasmas • Determine direction of rotation in JET diverted plasmas • Establish under which conditions co- and counter-current rotation arises in JET RF heated plasmas (F. Nave) CXRS Toroidal Angular Frequency Profiles for similar discharges, red (1st reliable profile after blip starts), blue (at the end of blip). Jerome Pamela Lisbon, 24 July 2007

  47. Modelling ITB plasmas Controlling ITB Oscillations in High-Performance Plasmas with a Dominant Fraction of Bootstrap Current (JPS Bizarro) It is shown that relaxation oscillations associated with repetitive ITB buildup and collapse in high-performance tokamak plasmas with ICRH, NBI, and LHCD and a dominant fraction of bootstrap current can be overcomeif the LHCD power is sufficiently high Jerome Pamela Lisbon, 24 July 2007

  48. Redistribution of ICRH Fast Ions Fast ion losses associated with MHD activity and sawtooth crashes were successfully measured (F Nabais) BeforeTornados AfterTornados During Sawtoth Crash Typical losses for TAE+ Precessional / Hybrid Fishbones Typical losses for TAE+ Tornados + Diamagnetic Fishbones Jerome Pamela Lisbon, 24 July 2007

  49. Simulations with COCONUT have confirmed previous results that D gas puffing helps avoiding radiative collapse ELMs are an important factor for an effective removal of impurities from the ETB and main SOL to the divertor region Modelling of impurity transport Numerical simulations of recycling impurity screening on JET (P Belo) Core Neon Concentration [%] 3 Deuterium puff levels TIME Core Neon Concentration for three deuterium puff levels; H-mode plasmas with (continuous line) and without ELMs (shaded line) Jerome Pamela Lisbon, 24 July 2007

  50. Recent correlation reflectometry measurements in JET show a clear decrease of the radial correlation length in the region inside the ITB foot, which is compatible with a reduction of turbulence in the plasma core Radial correlation reflectometry in JET Correlation reflectometry in plasmas with ITB (A.Figueiredo) Jerome Pamela Lisbon, 24 July 2007

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