Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching Convención SNC-Lavalin, Barcelona Laboratorio Nacional de Fusión CIEMAT Spanish Fusion Programme Strategic view

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

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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching Stellarator research at CIEMAT: TJ-II (1998)

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching TJ-II Helical axis stellarator The “lithium breakthrough” 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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching TJ-II results shown at IAEA FEC 2010 summary report 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 E r shear If zonal flows important: effect of RMP coils on H threshold?

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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.

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching TJ-II in the Fac Rev Report

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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  ) Role of magnetic topology (shear, rationals…) + stellarator reactor & power plant studies

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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€ The quest for TJ-III

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching TJ-III engineering design TJ-III construction Start 2022 TJ-III physics design Configuration studies (Reactor relevant) ? EU prog TJ-II full performance EBW, Li, Divertor, HIBP2 High , stability, impurity, turbulence transport, magnetic topology TJ-II gradually reduced effort W7X collab., JT60, EUsat Participation ITER Theory developments: numerical tokamak/stellarator One decade roadmap: plasma physics at CIEMAT Stellarator reactor, DEMO and power plant studies

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching Materials: structural / functional plasma facing Remote Handling Breeding blankets technology An increased effort in Fusion Technology CIEMAT strategic decision taken in 2006 National grant : Dual coolant blanket and auxiliary systems Collaborators from 12 institutions Strong effort on ODS, W, Eurofer SiC/SiC, insulators, W oxide resistant

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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching Shared by the facilities review Panel

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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 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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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: 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») 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 Parametric studies Investment ~ 20 M€

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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 Interaction Chamber (IC): Change in impact angle Cooling. Heating of samples IR+visible cameras… Transport of samples under vacuum? PILOT PSI-like parameters Pulsed up to 1.6T (0.4s) 0.2T in steady-state 2 roots pumps with total pumping speed 7200 m 3 /h Pressure 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 QSPA parameters (MJ/m 2 range) Pulsed duration: < 500 µs Plasma current: < 650 ka Ion energy: < 1 keV Electron density: – cm -3 Electron temperature: 3 – 5 eV (< 100 eV at sample) Energy density: > 2 MJ/m 2 Magnetic field at sample: 1 T Repetition period: 1- 3 min LP QSPA IC Collinear PILOT PSI QSPA plasma source PALOMA: A PWI Facility for Reactor Materials Studies Synergistic effects of high power & particle irradiation not tested !! Investment ~ 5 M€

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 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 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

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching The Technofusion Team > 70 persons (most of them part time) 60% non-CIEMAT

Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching Spanish industry commitment towards the Fusion programme 2007 ENSA Fabrication for TBM components IberdrolaWelding procedures VV ElyttHe manifold for ITER TF coils IberdrolaRH test facilities for Fusion AccionaConcrete structures for Fusion (n shield) IdomLiquid metal systems for Fusion 2008 Tecnatom Irradiation sensors for ITER IdomFeasibility of Technofusion triple beam Elytt Cyclotron for Technofusion triple beam ElyttIon source for Technofusion triple beam 2010 SENERVacuum permeator for T extraction EEAAT plant control with ECOSIMPRO SGENIA Magnetic sensors for Fusion IDOM IFMIF beam dump IDOM coupling MCNP/ Ansys/Fluent for Fusion TTIRF for IFMIF ENSA e- beam welding for fusion components NATEC Welding characterization for Fusion components Mec Buelna First Wall panels for ITER AccionaPolymer-reinforced concrete for Fusion GAMCSimulation for Fusion Ministry of Science R&D grant programme : CIEMAT / Industry collaborations Most companies members of the Spanish Fusion Technology Platform Second, (after FR) in number of tenders to F4E calls Third, (after IT,FR) in accumulated budget awarded by F4E