Spanish Fusion Programme Strategic view Convencin Spanish SNCLavalin

Spanish Fusion Programme Strategic view Convención Spanish. SNC-Lavalin, Programme Strategy Barcelona 14. 03. 2008 Laboratorio Nacional de Fusión CIEMAT EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Spanish strategy TJ-II W 7 X TJ-II sucessor Concept improvement JET P a r t i c i p a t ITER ion 1983 Power DEMO Plant EU SAT JT 60 Technology B. Approach (> 40 M€) Spanish Programme Strategy IFMIF Technofusion EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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) Issues: concept maturity, coil complexity, exhaust solution, impurity accumulation. Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Stellarator research at CIEMAT: TJ-II (1998) Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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 The “lithium breakthrough” • Global confinement physics in stellarators, role of magnetic topology • Plasma wall interaction • Diagnostics development • Theory & modelling Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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 If zonal flows important: effect of RMP coils on H threshold? TJ-II results shown at IAEA FEC 2010 summary report Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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 13. 04. 2011

TJ-II in the Fac Rev Report Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Stellarator line: Near Future Physics Plans Progress on stellarator Physics, (in support and complementary to W 7 X) • 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 Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

The scientific case for a TJ-III device • W 7 X provides the most advanced, reactor relevant configuration. TJ-III would take the basic principle of W 7 X design: reactor relevant 3 D 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 13. 04. 2011

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 ~ 50 M€ Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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). iota • Example of optimzed 3 period compact shearless quasi-isodynamic stellarator. • Mercier and Ballooning stable • NC transport at the level of quasi-symmetric device. Spanish Programme Strategy r/a EU Fusion Roadmap Workshop, Garching 13. 04. 2011

One decade roadmap: plasma physics at CIEMAT 2010 2012 2014 TJ-II full performance EBW, Li, Divertor, HIBP 2 High b, stability , impurity, turbulence transport, magnetic topology TJ-III physics design Configuration studies (Reactor relevant) 2016 2018 2020 TJ-II gradually reduced effort W 7 X collab. , JT 60, EUsat Participation ITER TJ-III engineering design ? TJ-III construction Start 2022 EU prog Theory developments: numerical tokamak/stellarator Stellarator reactor , DEMO and power plant studies Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

An increased effort in Fusion Technology CIEMAT strategic decision taken in 2006 • Materials: • structural / functional • plasma facing Strong effort on • ODS, W, Eurofer • Si. C/Si. C, insulators, W oxide resistant • Remote Handling • Breeding blankets technology Spanish Programme Strategy National grant 2008 -12: Dual coolant blanket and auxiliary systems Collaborators from 12 institutions EU Fusion Roadmap Workshop, Garching 13. 04. 2011

An increased effort in Fusion Technology CIEMAT strategic decision taken in 2006 Strong effort on • Materials: • ODS, W, Eurofer • structural / functional • plasma facing • Si. C/Si. C, insulators, W oxide resistant • Remote Handling • Breeding blankets technology Included in national list of priority research infrastructures 2007 Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Shared by the facilities review Panel Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

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 13. 04. 2011

MIRIAM – Triple beam ion irradiation facility • Advantages: Parametric Low activation experiment studies 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» ) 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€ Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

PALOMA: A PWI Facility for Reactor Materials Studies Linear Plasma Device (LP): • • • Cascade arc, superconducting field (1 T) 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 LP IC PILOT PSI QSPA parameters (MJ/m 2 range) • Pulsed duration: < 500 µs • Plasma current: < 650 ka • Ion energy: < 1 ke. V • Electron density: 1015 – 1016 cm-3 • Electron temperature: 3 – 5 e. V (< 100 e. V at sample) • Energy density: > 2 MJ/m 2 • Magnetic field at sample: 1 T • Repetition period: 1 - 3 min QSPA plasma source PILOT PSI-like parameters • Pulsed up to 1. 6 T (0. 4 s) • 0. 2 T in steady-state • 2 roots pumps with total pumping speed 7200 m 3/h • Pressure 0. 1 -1 Pa during plasma operation • Power fluxes > 30 MW/m 2 • Already achieved ITER-like fluxes, first 5 cm of ITER target (5 mm SOL) can be simulated • + beam expansion by B tailoring: Still high flux density and large beam 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? Spanish Programme Strategy Investment ~ 5 M€ Collinear EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Techno. Fusion: 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 Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

The Technofusion Team > 70 persons (most of them part time) 60% non-CIEMAT Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011

Spanish industry commitment towards the Fusion programme • Second, (after FR) in number of tenders to F 4 E calls • Third, (after IT, FR) in accumulated budget awarded by F 4 E Ministry of Science R&D grant programme 2007 -10: CIEMAT / Industry collaborations Most companies members of the Spanish Fusion Technology Platform 2010 2007 ENSA Iberdrola Elytt Iberdrola Acciona Idom Fabrication for TBM components Welding procedures VV He manifold for ITER TF coils RH test facilities for Fusion Concrete structures for Fusion (n shield) Liquid metal systems for Fusion 2008 SENER EEAA SGENIA IDOM TTI Vacuum permeator for T extraction T plant control with ECOSIMPRO Magnetic sensors for Fusion IFMIF beam dump coupling MCNP/ Ansys/Fluent for Fusion RF for IFMIF ENSA e- beam welding for fusion components NATEC Welding characterization for Fusion components Tecnatom Irradiation sensors for ITER Idom Feasibility of Technofusion triple beam Mec Buelna First Wall panels for ITER Elytt Cyclotron for Technofusion triple beam Ion source for Technofusion triple beam Acciona Polymer-reinforced concrete for Fusion GAMC Simulation for Fusion Spanish Programme Strategy EU Fusion Roadmap Workshop, Garching 13. 04. 2011