EU-PWI Taskforce EU-PWI Taskforce Summary of the Summary of the PSI facility review meeting PSI 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
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EU-PWI Taskforce EU PWI TF Meeting Nov. 4 – 6, 2009, Warsaw Summary of the PSI facility review meeting presented by R. Neu based on the Summary of the.
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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
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
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
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
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)