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PALOMA Facility TechnoFusión FL Tabarés JA Ferreira Owner consortium between Madrid Regional government and National Government based on the technical expertise from CIEMAT and UPM ID: 322873

plasma irradiation iter ion irradiation plasma ion iter material beam cm3 madrid qspa design technofusion fusion materials based characterization

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Slide1

Present status of PALOMA Facility (TechnoFusión)

F.L.

Tabarés

, J.A. FerreiraSlide2

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

usersIt has to be a Facility, i.e. should be based on large-scale equipment and infrastructure not affordable for small research groupsThe coordination with the European Fusion Programme must be assured

TechnoFusion Project: IdeaSlide3

To increase the Spanish involvement in the International Fusion ProgramTo develop the Spanish technology

It

should be useful in other research and technological areasWhereas 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 stageTechnology and basic understanding for the next step (DEMO)

R&D complementing the research in ITER

TechnoFusion Project: ObjectivesSlide4

R&D Areas of TechnoFusionSlide5

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

AdministrationSlide6

3 Locations: Leganés (South Madrid)

Leganés

Material Production and Processing

Characterization TechniquesSlide7

3 Locations: CIEMAT

11-12

20

F

Madrid I

Madrid II

Ion accelerators (Material irradiation)

Characterization techniques

Plasma-Wall Interaction

Characterization techniquesSlide8

24th January 2011: Sign of the agreement for the foundation of TechnoFusion Consortium by CIEMAT, UC3M and UPM

Last NewsSlide9

Material Irradiation AreaGOAL

 To reproduce neutron effects using accelerators

H and He generated in fusion (1 ppm/week of He in Fe) using implantation of H and HeDisplacements (dpa’s) using high energy ions of the target materialTriple beam irradiation zoneSingle 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 - 11Slide10

 

Heavy Ion Accelerator

Cyclotron k=110

Light Ion Accelerator

4 MV Light Ion Accelerator 6 MV

Irradiated MatrerialDepth(µm)

Ion

Energy

(MeV)

Ion

Energy (MeV)

Ion

Energy

(MeV)

Fe (7.8 g/cm

3

)

26.6

Fe

385

H

2.5

He

10

W (19.3 g/cm

3

)

10.1

W

373

H

1.6He6

C (2.3 g/cm3)148C96H4.5He18SiO2 (2.2 g/cm3)175Si

337H

4.6

He

18

SiC (3.2 g/cm

3

)

122.4

Si

337

H

4.6

He

18

SiC (3.2 g/cm

3

)

122.4

Si

337

D

4.6

He

18

Material

IrradiationSlide11

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 foundCommon issues:

Components of transport lines Neutralizer Beam energy degrader…Probably some prototypes will be needed

Material Irradiation AreaSlide12

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 conditionsBackground:

Particle fluxes at the divertor in ITER and in reactors: > 1024 ions/m2.sTransient 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 AreaSlide13

Plasma-Wall Interaction Area

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 µsPlasma current: < 650 kaIon energy: < 1 keV

Electron density: 1015 – 1016 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 minSlide14

Plasma Gun (QSPA)

Design Completed by Kharkov IPP team in collaboration with CIEMAT

Ready for prototypingSlide15

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

)Slide16

QSPA needs an expansion chamber

 pumping (incompatible with coils)

Interconnection of both machinesSlide17

Sample Chamber ConceptThe sample should be mounted on a rail that allow the exposure to both plasmas alternatively

Interconnection of both machinesSlide18

NbTi

coils cooled by

cryocoolers

Coil design

 

Material

Volume

Surface

Coil

NbTi

6,4e-4 m

3

0,10 m

2

Conductor

C10200 (OF copper)

5,0e-4 m

3

0,14 m

2

Heat shield

C10200

8,0e-4 m

3

0,27 m

2

Outer cryostat

304L MLI interior

1,0e-3 m

3

0,36 m

2Table 2. Geometrical characteristicsSlide19

Technology based on existing devicesThe most demanding part involving the integration of both systemsWaiting for funding…

Conclusions