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Present status of PALOMA Facility ( TechnoFusión ). F.L. Tabarés , J.A. Ferreira. TechnoFusion Project: Idea. Owner: consortium between Madrid Regional government and National Government, based on the technical expertise from CIEMAT and UPM
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Present status of PALOMA Facility (TechnoFusión) F.L. Tabarés, J.A. Ferreira
TechnoFusion Project: Idea 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: Objectives • 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
3 Locations: Getafe (South Madrid) • Material irradiation • Liquid Metal Technologies • Remote handling under irradiation • Characterization techniques • Computational simulation • Administration Getafe II Getafe I • Remote handling: Big prototipes
3 Locations: Leganés (South Madrid) Leganés • Material Production and Processing • Characterization Techniques
3 Locations: CIEMAT 11-12 • Ion accelerators (Material irradiation) • Characterization techniques Madrid I Madrid II 20F • Plasma-Wall Interaction • Characterization techniques
Last News 24th January 2011: Sign of the agreement for the foundation of TechnoFusion Consortium by CIEMAT, UC3M and UPM
Material Irradiation Area • GOAL To reproduce neutron effects using accelerators • H and He generated in fusion (1 ppm/week of He in Fe) using implantation of H and He • 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
Material Irradiation Area • 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
Plasma-Wall Interaction Area 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:> 1024 ions/m2.s Transient thermal loads (ELMS and disruptions): ~ MJ/m2 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 PWI Components • 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: STCU Partner Contract 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
Plasma Gun (QSPA) • Design Completed by Kharkov IPP team in collaboration with CIEMAT • Ready for prototyping
Linear device Three channel cascade arc plasma source: Description Collaboration with FOM (Eider Oyarzabal) • 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.
Interconnection of both machines QSPA needs an expansion chamber pumping (incompatible with coils)
Interconnection of both machines Sample Chamber Concept The sample should be mounted on a rail that allow the exposure to both plasmas alternatively
Coil design NbTi coils cooled by cryocoolers
Conclusions Technology based on existing devices The most demanding part involving the integration of both systems Waiting for funding…