Present status of PALOMA Facility (TechnoFusión)

F.L. Tabarés, J.A. Ferreira

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

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

R&D Areas of TechnoFusionMaterials

Irradiation

Plasma/wall

Interaction

Liquid Metals

Technologies

Remote Handling

Characterization

Techniques

Materials Production

& Processing

Computational

Simulation

3 Locations: Getafe (South Madrid)

Getafe I

Getafe II

Remote handling: Big prototipes

Material irradiationLiquid Metal TechnologiesRemote handling under irradiationCharacterization techniquesComputational simulationAdministration

3 Locations: Leganés (South Madrid)

LeganésMaterial Production and ProcessingCharacterization Techniques

3 Locations: CIEMAT

11-12

20F

Madrid I

Madrid II

Ion accelerators (Material irradiation)Characterization techniques

Plasma-Wall InteractionCharacterization techniques

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

Last News

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

1.E-03

1.E-02

1.E-01

1.E+00

1.E+01

1.E+02

1.E+03

1.E-03 1.E-02 1.E-01 1.E+00 1.E+01 1.E+02

Desplazamientos [DPA/ semana]H

e[ap

pm/s

eman

a]

HTTR

PWD

JMTRJOYO

ITER

DEMOIFMIF (MF)

IFMIF (HF)

Fe

BOR60

XADS (1MW)

ESS

HFR Petten(position f8)

SPIRAL 2

SNS (p+n)

BR2 Mol

TECHNOFUSI ON

  Heavy Ion AcceleratorCyclotron

k=110

Light Ion Accelerat

or4 MV

Light Ion Accelerato

r 6 MV

Irradiated

Matrerial

Depth

(µm)Ion

Energy

(MeV)Ion

Energy

(MeV)Ion

Energy

(MeV)

Fe (7.8 g/cm3)

26.6Fe

385 H 2.5 He 10

W (19.3 g/cm3)

10.1W

373 H 1.6 He 6

C (2.3 g/cm3)

148C

96 H 4.5 He 18

SiO2 (2.2 g/cm3)

175Si

337 H 4.6 He 18

SiC (3.2 g/cm3)

122.4

Si337 H 4.6

He 18

SiC (3.2 g/cm3)

122.4

Si337 D 4.6

He 18

Material Irradiation

104

105

106

107

108

109

10-5 0,001 0,1 10 1000

CW

Act

ivity

(B

q)t (days)

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

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

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 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

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:

DescriptionThree 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)

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

Interconnection of both machines

Vacuum Vacuum

DiagnosticdevicesWindow

Sample chamber(Expansion chamber)

d ≥ 1m

Linearplasma target Isolation

valve

Vacuum

Rail

Superconductingcoils

Pulsedplasma

Vacuum Vacuum

DiagnosticdevicesWindow

Sample chamber(Expansion chamber)

d ≥ 1m

Linearplasma target Isolation

valve

Vacuum

Rail

Superconductingcoils

Pulsedplasma

Vacuum Vacuum

DiagnosticdevicesWindow

Sample chamber(Expansion chamber)

d ≥ 1m

Linearplasma target Isolation

valve

Vacuum

Rail

Superconductingcoils

Superconductingcoils

Pulsedplasma

2 1 2’ 0

a)

2 1 2’ 0

c.1)

2 1 2’ 0

b)

2 1 2’ 0

c.2)

NbTi coils cooled by cryocoolers

Coil design

  Material Volume SurfaceCoil NbTi 6,4e-4 m3 0,10 m2

Conductor C10200 (OF copper)

5,0e-4 m3 0,14 m2

Heat shield C10200 8,0e-4 m3 0,27 m2

Outer cryostat

304L MLI interior

1,0e-3 m3 0,36 m2

Table 2. Geometrical characteristics

Technology based on existing devices The most demanding part involving the

integration of both systems Waiting for funding…

Conclusions