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)