1. Present status of PALOMA Facility (TechnoFusión) F.L. Tabarés, J.A. Ferreira

2.  Owner: consortium between Madrid Regional government and National Government, based on the technical expertise from CIEMAT and UPM  It has to be a Facility, open to Spanish and European users  It has to be a Facility, i.e. should be based on large- scale equipment and infrastructure not affordable for small research groups  The coordination with the European Fusion Programme must be assured TechnoFusion Project: Idea

3.  To increase the Spanish involvement in the International Fusion Program  To develop the Spanish technology  It should be useful in other research and technological areas Whereas ITER construction is mainly based on today´s technology the focus of TechnoFusion will be on:  Development of technologies to be used in ITER at later stage  Technology and basic understanding for the next step (DEMO)  R&D complementing the research in ITER TechnoFusion Project: Objectives

4. R&D Areas of TechnoFusion

5. 3 Locations: Getafe (South Madrid) Getafe I Getafe II Remote handling: Big prototipes Material irradiation Liquid Metal Technologies Remote handling under irradiation Characterization techniques Computational simulation Administration

6. 3 Locations: Leganés (South Madrid) Leganés Material Production and Processing Characterization Techniques

7. 3 Locations: CIEMAT 11-12 20 F Madrid I Madrid II Ion accelerators (Material irradiation) Characterization techniques Plasma-Wall Interaction Characterization techniques

8.  24 th January 2011: Sign of the agreement for the foundation of TechnoFusion Consortium by CIEMAT, UC3M and UPM Last News

9. Material Irradiation Area  GOAL  To reproduce neutron effects using accelerators 1.H and He generated in fusion (1 ppm/week of He in Fe) using implantation of H and He 2.Displacements (dpa’s) using high energy ions of the target material  Triple beam irradiation zone  Single beam operation to irradiate under high magnetic field  Several simple/double lines to irradiate at different temperatures (“in beam” measurements) MAIN CONDITIONS: Reach IFMIF values of irradiation (0,1 dpa/week) Reach He/dpa ratios ~5 - 11

10. Heavy Ion Accelerator Cyclotron k=110 Light Ion Accelerator 4 MV Light Ion Accelerator 6 MV Irradiated Matrerial Depth (µm) Ion Energy (MeV) Ion Energy (MeV) Ion Energy (MeV) Fe (7.8 g/cm 3 ) 26.6 Fe 385H2.5He10 W (19.3 g/cm 3 ) 10.1 W 373H1.6He6 C (2.3 g/cm 3 )148 C 96H4.5He18 SiO 2 (2.2 g/cm 3 ) 175 Si 337H4.6He18 SiC (3.2 g/cm 3 ) 122.4 Si 337H4.6 He18 SiC (3.2 g/cm 3 ) 122.4 Si 337D4.6 He18 Material Irradiation

11.  Conceptual design in progress !!  Linear accelerators: commercially available, but some issues has still to be solved in the near term, as the ion sources (types, currents,…)  Cyclotron : Isochronous multi-ion (complex!!). Detailed design needed:  Possibly SC type. Estimations are in progress  External Collaborations has been created (MIT, GANIL…) but finally a constructor will have to be found  Common issues:  Components of transport lines  Neutralizer  Beam energy degrader…  Probably some prototypes will be needed Material Irradiation Area

12. To reproduce the real, harsh, environment under which materials will be exposed to the plasma in a fusion reactor (ITER/DEMO): - ELMs+Disruption parameters reproduction - Capability to study PW effects in materials previously irradiated at the Ion Accelerator Complex with heavy ions H+ He+ (“low activation” irradiation) - Studies of W samples irradiated to DEMO EoL equivalent conditions Background: Particle fluxes at the divertor in ITER and in reactors: > 10 24 ions/m 2.s Transient thermal loads (ELMS and disruptions): ~ MJ/m 2 Temperature between transients: few 100 ºC (not loaded areas) to1500 ºC (loaded areas) Frequency and duration & of transients: few Hz to one every several pulses, 0.1-10 ms ITER FW materials: CFC, W, Be DEMO FW materials: W, SiC, Liquid metals(?)…. Neutron damage at the end of operation lifetime: 1 dpa Plasma-Wall Interaction Area

13. PWI Components 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 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 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 Plasma Gun (QSPA): Compact QSPA type: STCU Partner Contract with Kharkov IPP QSPA parameters (MJ/m 2 range) Pulsed duration: < 500 µs Plasma current: < 650 ka Ion energy: < 1 keV Electron density: 10 15 – 10 16 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

14. Plasma Gun (QSPA)  Design Completed by Kharkov IPP team in collaboration with CIEMAT  Ready for prototyping

15. Linear device Three channel cascade arc plasma source: Description Three separate cathodes. Three separate gas inlets. Distance between the channels: 20 mm. Channel diameter: 5mm. Nozzle diameter: 5, 5.5 and 6 mm. Shared water cooling. Collaboration with FOM (Eider Oyarzabal)

16.  QSPA needs an expansion chamber  pumping (incompatible with coils) Interconnection of both machines

17. Sample Chamber Concept  The sample should be mounted on a rail that allow the exposure to both plasmas alternatively Interconnection of both machines

18.  NbTi coils cooled by cryocoolers Coil design MaterialVolumeSurface CoilNbTi6,4e-4 m 3 0,10 m 2 ConductorC10200 (OF copper) 5,0e-4 m 3 0,14 m 2 Heat shieldC102008,0e-4 m 3 0,27 m 2 Outer cryostat304L MLI interior 1,0e-3 m 3 0,36 m 2 Table 2. Geometrical characteristics

19.  Technology based on existing devices  The most demanding part involving the integration of both systems  Waiting for funding… Conclusions