Convención SNC-Lavalin, Barcelona 14.03.2008

1. Spanish Fusion Programme Strategic view Laboratorio Nacional de Fusión CIEMAT Convención SNC-Lavalin, Barcelona 14.03.2008

2. Spanish strategy TJ-II W7X TJ-II sucessor Concept improvement Power Plant P a r t i c i p a t i o n DEMO JET 1983 ITER EU SAT JT60 Technology B. Approach (> 40 M€) Technofusion IFMIF

3. Issues: concept maturity, coil complexity, exhaust solution, impurity accumulation. Stellarator as a Reactor: potential advantages • Steady state: material fatigue, energy storage, HT superconductors • Current free: no central solenoid, no need for high power control systems & coils • No disruptions: forces, dust generation, runaway jets, safety case: cost • Low or no CD needs: low recirculating power, avoid, possibly, bulky NBIs • No large ELMs (tbc): erosion, control coils. • High ne low Te operation: fusion power, lower divertor loads, better pellet penetration (also more feasible HFS)

4. Stellarator research at CIEMAT: TJ-II (1998)

5. TJ-II Helical axis stellarator • TJ-II has produced since its start in 1998 a significant scientific contribution, mainly in the areas of • Turbulence transport • Global confinement physics in stellarators, role of magnetic topology • Plasma wall interaction • Diagnostics development • Theory & modelling The “lithium breakthrough”

6. H-mode discovered 30 years ago, not yet a clear explanation for L-H transition-> threshold (ITER) Contribution to the understanding of the L-H transition mechanism: suppression of ñ precedes onset of Er shear TJ-II results shown at IAEA FEC 2010 summary report If zonal flows important: effect of RMP coils on H threshold?

7. TJ-II strategy • Contributions to Tokamak and basic physics derived from the capabilities of TJ-II • Development of the stellarator concept as a realistic solution for a commercial fusion reactor • Training, education and mobilization of national resources towards fusion • Small and midsize national devices: • High physics/€€ or training/€€ ratio. • High flexibility and quick reaction time. • Contribute to national support to the EU Fusion Programme • Reducing the programme to the largest machines is not always the most efficient solution.

8. TJ-II in the Fac Rev Report

9. Stellarator line: Near Future Physics Plans Progress on stellarator Physics, (in support and complementary to W7X) • Power & particle exhaust: divertor concept • Flux expansion divertors • Role of Liquid Li limiters & Li coatings • Impurity accumulation • High density High confinement modes • Lithium as plasma facing element (low Z) • Coil complexity & distance to plasma • Relaxing constraints on optimized configurations: • Stability limits (high b) • Role of magnetic topology (shear, rationals…) • + stellarator reactor & power plant studies

10. The scientific case for a TJ-III device • W7X provides the most advanced, reactor relevant configuration. TJ-III would take the basic principle of W7X design: reactor relevant 3D optimisation • Significant step forward in computer & optimisation resources: allowing for engineering parameters (coil geometry and coil plasma clearance) to be part of the optimization loop

11. The quest for TJ-III • - Release constraints on stability requirements, magnetic shear and bootstrap current • Introduce simplified turbulent transport simulations in the optimisation (or full simulations, EUTERPE-like in selected cases) • Search for alternative divertor solutions (flux expansion, Liquid Li) • Establish reactor relevance of a down-scaled experiment • Not a long pulse device (copper coils), size similar to TJ-II • Using existing building, power supplies and some aux. systems cost could be kept in the order of ~ 50M€

12. The quest for TJ-III • Stellarator Optimization based on NC, Mercier and Ballooning stability. • Use of Grid computing (Fusion VO): Huge computing power. • Distributed Asynchronous Bee algorithm: Evolutionary algorithm that explores the phase space (like bees in nature). • Example of optimzed 3 period compact shearless quasi-isodynamic stellarator. • Mercier and Ballooning stable • NC transport at the level of quasi-symmetric device. iota r/a

13. ? One decade roadmap: plasma physics at CIEMAT 2010 2012 2014 2016 2018 2020 TJ-II full performance EBW, Li, Divertor, HIBP2 High b, stability , impurity, turbulence transport, magnetic topology TJ-II gradually reduced effort W7X collab., JT60, EUsat Participation ITER TJ-III physics design Configuration studies (Reactor relevant) TJ-III engineering design TJ-III construction Start 2022 EU prog Theory developments: numerical tokamak/stellarator Stellarator reactor , DEMO and power plant studies

14. An increased effort in Fusion Technology CIEMAT strategic decision taken in 2006 • Strong effort on • ODS, W, Eurofer • SiC/SiC, insulators, W oxide resistant • Materials: • structural / functional • plasma facing • Remote Handling • Breeding blankets technology National grant 2008-12: Dual coolant blanket and auxiliary systems Collaborators from 12 institutions

15. Included in national list of priority research infrastructures 2007 An increased effort in Fusion Technology CIEMAT strategic decision taken in 2006 • Strong effort on • ODS, W, Eurofer • SiC/SiC, insulators, W oxide resistant • Materials: • structural / functional • plasma facing • Remote Handling • Breeding blankets technology

16. Shared by the facilities review Panel

17. Could be tested with existing fission sources: known Eurofer properties Very important for mechanical behaviour Combined effect: requires high energy neutrons (14 Mev). Could simulation only do the job? • Effect can be simulated with accelerators (triple beam) • Same species ( i.e. Fe ) for the dpa´s • He and H beams for implanting the gas Filling the gap until the first IFMIF results Optimistic scenario: start >2015, finish >2022, first full power irradiations >2024, first irradiation results > 2026 • How to progress during the next 15 years with the effects of irradiation: • Activation • Dpa´s • H & He generation

18. MIRIAM – Triple beam ion irradiation facility • Advantages: Low activation experiment Adjustable He/dpa and H/dpa ratio Adjustable wide range of dpa rate One irradiation takes 2 weeks (comp. with 2 years on IFMIF) • Disadvantages Limited range: 20-25 microns depth (but at least a few grains of most of materials of interest) (MIRIAM: tens of microns –one order of magnitude higher than any other triple beam facility and «quasi-volumetric») Parametric studies • Mission: • Maximize the possibilities that the first batch of IFMIF tests has the right material • Try to discover early enough any surprises which might arise with our reference materials • Provide experimental validation for multiscale modelling Investment ~ 20 M€

19. LP IC QSPA PALOMA: A PWI Facility for Reactor Materials Studies • PILOT PSI-like parameters • Pulsed up to 1.6T (0.4s) • 0.2T in steady-state • 2 roots pumps with total pumping speed 7200 m3/h • Pressure 0.1-1 Pa during plasma operation • Power fluxes > 30 MW/m2 • Already achieved ITER-like fluxes, first 5 cm of ITER target (5mm SOL) can be simulated • + beam expansion by B tailoring: Still high flux density and large beam • Linear Plasma Device (LP): • Cascade arc, superconducting field (1T) • PILOT-PSI design. Upgrade to larger Beam (FOM Collaboration) • Steady-state, superconductor (commercial available) • UHV pumped (impurity control) • A+M Physics studies and diagnostic development for divertors • Plasma Gun (QSPA): • Compact QSPA type: Development under collaboration with Kharkov IPP • QSPA parameters (MJ/m2 range) • Pulsed duration: < 500 µs • Plasma current: < 650 ka • Ion energy: < 1 keV • Electron density: 1015 – 1016 cm-3 • Electron temperature: 3 – 5 eV (< 100 eV at sample) • Energy density: > 2 MJ/m2 • Magnetic field at sample: 1 T • Repetition period: 1- 3 min PILOT PSI QSPA plasma source Synergistic effects of high power & particle irradiation not tested !! • Interaction Chamber (IC): • Change in impact angle • Cooling. Heating of samples • IR+visible cameras… • Transport of samples under vacuum? Investment ~ 5 M€ Collinear

20. TechnoFusion: 2010 highlights and present status • Pre-engineering design of main buildings finished • Starting engineering design of complex systems (Triple beam and plasma wall facilities) including validation experiments Present situation: - Recently established the legal consortium structure to launch the project Budget: Due to constrains in the financial situation the budget for 2011-12 will be around 3-5 M€ (total) - We need to define in more detail the priorities and to start the acquisition of some equipment as well as the engineering design of complex components

21. The Technofusion Team > 70 persons (most of them part time) 60% non-CIEMAT

22. Spanish industry commitment towards the Fusion programme • Second, (after FR) in number of tenders to F4E calls • Third, (after IT,FR) in accumulated budget awarded by F4E Ministry of Science R&D grant programme 2007-10: CIEMAT / Industry collaborations Most companies members of the Spanish Fusion Technology Platform 2010 SENERVacuum permeator for T extraction EEAA T plant control with ECOSIMPRO SGENIA Magnetic sensors for Fusion IDOM IFMIF beam dump IDOM coupling MCNP/ Ansys/Fluent for Fusion TTI RF for IFMIF ENSA e- beam welding for fusion components NATEC Welding characterization for Fusion components Mec Buelna First Wall panels for ITER Acciona Polymer-reinforced concrete for Fusion GAMC Simulation for Fusion 2007 ENSA Fabrication for TBM components Iberdrola Welding procedures VV Elytt He manifold for ITER TF coils IberdrolaRH test facilities for Fusion Acciona Concrete structures for Fusion (n shield) IdomLiquid metal systems for Fusion 2008 Tecnatom Irradiation sensors for ITER Idom Feasibility of Technofusion triple beam Elytt Cyclotron for Technofusion triple beam Elytt Ion source for Technofusion triple beam