EU-PWI TaskforceEU-PWI Taskforce

Summary of the Summary of the PSI facility review meetingPSI facility review meeting

presented by R. Neu

based on the ‘Summary of the EFDA Technical Meeting on European facilities

for Plasma Surface Interaction (PSI)’by the EFDA Leader

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 2

Purpose of meeting

Meeting in Garching on 18/6/2009 organized by EFDA

• to assess the existing and projected Plasma-Surface Interaction (PSI) facilities and related laboratory activities in Europe,

• to avoid duplication and to focus on high priority facilities because scarcity of resources,

• to provide further programmatic background to support the on-going bilateral discussions between the EC and Associations.

• assessment supported by the PWI TF,

• performed solely on programmatic ground,

• funding issues were not addressed.

• >40 participants (17 Assoc.) + representatives of Commission, F4E, ITER

• > 20 talks

Report presented to members of EFDA steering committee on July 8 2008 in Barcelona

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 3

Categories of PSI facilities

type of facilities issues addressed

plasma simulators PSI issues in ITER relevant conditions: fuel retention, dust pro-duction, mixed material formation, erosion / redeposition, …

pulsed facilities (plasma guns …)

impact of ITER relevant transient heat loads (ELMs, disruptions) on plasma facing materials

high heat flux testing testing of plasma facing components performance under steady state heat loads, thermal cycling, critical heat flux

ion beam surface analysis facilities

ion irradiation of samples for elementary processes study (erosion, fuel retention …)Simulation of neutron impact damagePost mortem analysis of components exposed in tokamaks or plasma simulators (fuel content etc …).

facilities with capa-bility of investigating toxic and/or irradiated materials

post mortem analysis of ITER relevant materials : Be components, neutron irradiated or T contaminated samples …

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 4

Requirements for plasma simulators

• low temperature plasmas corresponding to ITER semi detached divertor scenario

• high fluence to match ITER long pulse/high fluence conditions, in particular for fuel retention studies

• high target surface temperatures• ability to handle toxic/irradiated materials

(no capacity in EU at the moment for Be samples, neutron irradiated samples)

• transient heat and particle loads in addition to steady state plasma/power loads

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 5

Requirements for plasma simulators

Plasma density 1018 - 1022 m-3

Ion flux up to 1024 m-2s-1

Fluence 1026-1027 m2

Ti (eV)1 < 15 (for divertor study), <500 (for midplane FW study)

Te (eV)1 < 5 (divertor), < 200 (midplane)

Power flux up to 20 MW m-2

Magnetic field 2.5 - 5 T

Pulse duration 300-500 s up to Steady state

Plasma composition D, T, He, seeding imp. (Ne, Ar, N2 …), wall mat. (C, Be, W)

Beam size >2 cm

Target Materials: C, Be, W Flexible geometry (angle of incidence), gaps

target temperature 120 - 1000 °C (more for DEMO R&D), active cooling

Irrad. / toxic materials <1 dpa for ITER (more for DEMO R&D), Be, T1 steady state values. ELMs will lead to plasma temperatures up to 1 keV at the targets

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 6

  PISCES-B NAGDIS-II Pilot- PSI Vision I Magnum-PSI

Jule PalomaPlasma sim.

Association USA Japan FOM SCK.CEN FOM FZJ CIEMAT

Plasma Density (m-3) 1017 -1019 <1020 1019 -1021 1016 -1018 1019 -1021 1017 -1020 > 1020

Ion Flux (1024/m2/s) Up to 0.1 <0.1 <10 0.001 0.1-10 <0.1 <10

Fluence (1026 m-2) 0.1-10 1 <0.04 <1 <300 <10 <10

Ti (eV) [2] < 20 (300) <10 <5 <20 (500) <10 (more with biasing)

<10 <5

Te (eV) 2-40 <10 <5 10 0.1-10 <20 <5

Power flux (MW/m²) 1-10 <1 <30 10 0.1 <30

Magnetic Field (T) 0.02-0.1 0.25 1.6 0.2 3 0.1 1

Pulse length (s) SS SS 4 SS SS SS SS

Plasma composition D, Li, Be, C, W, N, Ne, Ar

H, He D,C,N,Ne,Ar, W, metals

D, T, C, W, Be, metals

D,Li,C,N,Ne,Ar, W, metals

D, C, W, metals

D, He, C, Ne, Ar, W,

metals

Beam size (cm) 2-3 1.5 ~20 10 5-10 2-5

Beryllium Yes No Yes No Yes No

T / n - irradiated mat. No/No No/ No Yes/Yes No /No Yes/ Yes No/No

Target temp. (°C) <1100 ? 1200 20-400 20-1500 1200 1200

Transients starting no starting no yes no yes

Availability operating operating operating 2011 2010 2015 2016

Capital Cost range[3]  C tbc A A (10 M€) B (6 M€)

Parameter space of existing / planned plasma simulators

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 7

Parameter space of existing / planned plasma simulators

JULE

PALOMA

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 8

Requirements for pulsed facilities

Plasma Parameters Disruption Unmitig. ELMs Mitigated ELMs

Energy Density (MJm-2) < 30 5-20 0.5-1

Power Density (GWm-2) < 13 20-40 1-2

Pulse duration (msec) 1.5-3 0.25-0.5 0.2-0.5

Plasma density (1020 m-3 ) ~100 ~10 ~1

Ion Energy (keV) < 0.5 1-2.5 1-2.5

Plasma pressure (bar) 0.05-0.1 0.05-0.1 <0.1

Magnetic Field (T) 2.5-5 2.5-5 2.5-5

Rep. rate for ELMs (Hz)ITER divertor: >106 events

~1 20-40

Additional important parameters• angle of incidence, gaps …• materials (C, Be, W)• Tsurf (120 - 1000 °C), active cooling• n-irradiated / toxic materials : ~1 dpa for ITER (> for DEMO), Be, T

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 9

Parameters of existing/planned pulsed devices

QSPA QSPA 2MK-200 PUMA PALOMA plasma

gun

Pilot PSI/ MAGNUM-PSI (pulsed casc. Arc)

Association / country RF Ukraine RF IPPLM CIEMAT FOM

Energy Dens. (MJm-2) 0.5-30 0.5-30 2 <100 2 1

Power Dens. (GWm-2) <100 2

Pulse duration (msec) 0.1-0.6 0.25 0.02 1-10 0.5 0.5

Plas. dens. (1020m-3) 100 100 1000 10-100 200

Ion Energy (keV) <0.1 0.4-0.9 10 1

Electron Temp. (eV) <10 10 <5 10

Plasma pressure (Pa) <0.1

Magnetic Field (T) <1 <0.7 1 5 1 1.6-3

Repetition rate (Hz) > 1 > 1 > 1 > 1 0.3-1 >1

Beam size (cm) 10 1 10 2

Availability operating operating operating 2013 2015 2010

Capital Cost range 7 M€ 4 M€ 0.15 M€

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 10

Requirements for high heat flux facilities

High heat flux facilities (HHFFs)• assessment of performance and lifetime of PFCs under steady state

heat loads and eventually “normal” transient events like small repetitive ELMs

• qualification of ITER PFCs

Necessary/desirable properties• good matching of energy density and pulse duration, very flexible beam

control, high repetition rate • investigation of synergistic effects (combination of thermal shock and

thermal fatigue loads)• testing of complete modules, including water cooling, interfaces and

temperature gradients• testing of steady state and transient heat loads• in-situ temperature (infra-red, TC) diagnostic, combined with ex-situ

metallurgy

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 11

Properties of existing HHFF

Facility particletype

particle energy[keV]

beampower[kW]

max. load.

area [m2]

powerdensity[GWm-2]

remarks instituteITER-

partner

status

TSEFEY e- 30 60 0.25 0.2 scanned beam, = 20 mm

beryllium tbc

EfremovRF

Operating ?

JUDITH1JUDITH2

e-120

30 - 6060

2000.010.25

10irradiated samples

berylliumFZJEU

Operating2010

FE 200 e- 200 200 1.0 60 scanned beam, 2 - 3 mm

hot coolant loop

CEAEU

Operating

JEBIS e- 100 400 0.18 2 beam sweeping 1 - 2 mm

JAEAJA

Operating

EB 1200 e- 40 1200 0.27 10 scanned beam, 2 - 12 mm

hot coolant loop

SNLAUS

operating

DATS H+, He+ 50 1500 0.1 0.06 2 ion sources at 0.75 MW

150 mm

JAEAJA

Operating

GLADIS H+, He+ 15-50 2200 0.3 0.05 2 ion sources at 1.1 MW

70 mm

IPPEU

Operating

MARION H+, He+ 60 5000 0.01 0.12 1 ion source at 5 MW 200 mm

FZJEU

Operating

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 12

Role of ion beam facilities

Ion beam facilities can be used in different areas of PSI research :• measurements of the elementary processes linked with ion

irradiation of materials with full control of the energy, impact angle, and species of bombarding ions, allowing the – production of databases of the atomic and molecular processes for

modelling codes,

– validation of computational simulations of elementary processes.

• simulation of the effect of neutron irradiation by creating damage at the surface of bombarded materials with high energy heavy ions (HI)

• post mortem analysis: NRA, RBS, ERDA, PIXE, …

(preferentially located close to PSI simulators or tokamaks, to avoid long term air exposure of the samples before analysis.

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 13

Properties of IBA facilities for PSI studies

IPP FOM MHEST VR UKAEA UKAEA TEKES CIEMAT ENEA ITN/IST CEA GANIL

Terminal voltage (MV)

3 3 2(tandem)

5 3 2.5 5 Linear I: 4

Linear II: 6 (tand.)

2.5 - > 20

3 3.5 Low / high energy range

Ion species

H,D, He, Li, His

H, He, O, HIs

H, He, Li, HIs

H,D, He,Be, C,O,

W

H, He H, D, He

H, C H, He, HIs

others

H, He, HIs

H,3He,4He, HIs

H,D,3He 4He

all species

RBS, PES Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes No

NRA Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes No

ERDA Yes Yes Yes Yes No Yes Yes Yes Yes Yes Yes No

HI damage Yes Yes No Yes No No Yes Yes Yes Yes No Yes

Be/T Yes No No Yes Yes Yes Yes No No Yes No No

large tiles Yes Yes No Yes Yes Yes ? No No No No Yes

µ beam No No Yes Yes No No No Yes Yes Yes Yes No

AMS No No No Yes No No Yes No No Yes No No

Insitu PSI Yes Yes No No No No No No No No Yes No

availability op. 2012 op. op. <2011 >2011 op. 2015/op. op. op. op. op.

PSI fract. % 100 100 50 25 >50 ~50 25 >75 25 >30 25 ~0

EU PWI TF meeting, Nov. 4-6, 2009, Warsaw R. Neu 14

Post mortem analysis facilities

Activity Associations

Tritium and Beryllium post mortem analysis facilities, activated materials

SCK-CEN, VR, UKAEA, TEKES, FZJ, IPP, AEUL, MEdC, CEA, IST

Ion Beam Analysis: NRA, RBS, PIXE, ERDA (micro beams)

VR, MHEST, UKEA, IPP, TEKES, CEA, IST

Spectroscopy & Microscopy: SEM-EDX, TDS, LIBS, SIMS, optical microscopy

TEKES, AEUL, ENEA, SCK-CEN, FZJ, IPP, CEA, IPPLM, IST

Deposition systems - samples production

MEdC (TVA method - Be, C, W), TEKES

Important capabilities of post mortem analysis facilities• Quantitative, well calibrated range of surface analysis methods• analysis of H-isotopes content for fuel retention studies• Be, C, W compositional analysis• Ability to treat large samples (full tiles from tokamaks)• Ability to treat toxic/ irradiated samples (Be, T)