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FZJ ressources and topics

Association EURATOM- FZJ CCE-Fu Workshop on European fusion roadmap for FP8 and beyond April 13-14 IPP Garching. FZJ ressources and topics. HPC-FF (IA). Theory + computational engineering. Objectives 1, 2+4. Plasma-wall interactions and plasma facing materials for ITER, W7-X + DEMO.

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FZJ ressources and topics

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  1. Association EURATOM- FZJCCE-Fu Workshop on European fusion roadmap for FP8 and beyondApril 13-14 IPP Garching

  2. FZJ ressources and topics HPC-FF (IA) Theory + computational engineering Objectives 1, 2+4 Plasma-wall interactionsandplasmafacingmaterialsfor ITER, W7-X + DEMO ITER construction and Fusion Power Plants Tokamak physics Objectives 1+4 W7-X construction

  3. Tokamak Physics:Plasma edge transport and PWI in 3D boundaries –relevant for both tokamaks and stellarators TEXTOR Dynamic Ergodic Divertor JET AUG MAST DIII-D • RMP ELM suppression / island divertor / non-axisymmetric boundary • understand transport and develop predictive modeling capabilities • benchmark experiments

  4. Theory, modelling and computational engineering Transition from 2D  3D edgemodelling (EMC3-EIRENE, B2-EIRENE, ERO) fordivertor design, addressing: Peak targetheatload Plasma purityand He removal Divertorregimes (detachment) Computationalengineeringfor ITER design Diagnosticmirrorerosionanddeposition Preparingdivertorcodesfor DEMO 1st mirror EIRENE code model via ANSIS interface (mirror lifetime assessment) 2nd mirror CXRS port plug, CATIA design

  5. Plasma wall interactions and plasma facing materials for ITER, W7-X and DEMO TEXTOR, JET ILW, JUDITH, …. MAGNUM-PSI, JULE-PSI • Lifetimeof wall components • Erosion and material migration • Meltlayerdynamicsof metallic PFMs • New concepts: developmentof in-situ metallic coatings, alternative targetconcepts, alternative wall materials (e.g. EUROFER) • Safety • Fuel retentionandfuelremoval, in-situ characterizationofsurfacelayers • Dustformation • PWI andedgetransport in 3D structures

  6. Plasma wall interactions and plasma facing materials for ITER, W7-X and DEMO New • Plasma wall interactions in nuclear environment: toxic (Be) and neutron damaged PFMs • integrated concept to test and qualify neutron irradiated and toxic plasma facing materials (PFMs) under high heat loads and plasma exposure in Jülich • Characterization and qualification of PFCs: Heat load experiments: • Transient heat loads onto metallic and carbon based PFMs, thermal fatigue of PFMs and synergetic effects • Development of new PFMs

  7. HML 1 HML 2 HML 3 10m 5m 0m Hot Materials Lab (HML) – at present being refurbished Hot Cells Controlled Area Access Area Offices JULE-PSI with target exchange and analysis station JUDITH 2 JUDITH 1 upgrade Hot Plasma Laboratory Non-nuclear twin Be surface analysis

  8. Development of modelling capabilities and benchmark of codes Retention in Be-W compounds Dust production Retention in n- damaged materials Mixed systems Be-C-W JULE-PSI Erosion of n-damaged PFMs, impact of surface morphology and micro-structure Re-erosion of Be deposits Surface diagnostics Analysis of Be/T samples (JET, ITER) JUDITH 1+2 Procurement and qualification testing Synergistic effects • Thermal fatigue and thermal shock • Thermal loads and plasma exposure Thermal fatigue tests Transient loads

  9. Research Facilities • In Jülich: • TEXTORtokamak, PWI testfacility, high riskexperiments • PSI-2 Jülich, linear plasmadevice, pilotexperimentfor JULE-PSI • MARION, ion beam facility • JUDITH 1 (Hot Cell), JUDITH 2 (Becapability), electron beam facility • JULE-PSI, JUDITH-1 upgrade in Hot Cell: , extendedcapabilitiesforsurfaceanalysisoftoxicandneutronactivatedmaterials • TEC plasmafacilities: MAGNUM-PSI, VISION-I and JET, Wendelstein 7-X, …

  10. Research Facilities, cont. • High performance computer for fusion HPC-FF (Implementing agreement, Aug. 2009 --- 31.4.2013) Intel-based Linux cluster 1,080 compute nodes, 8320 cores 101 Teraflop/s peak funded by EU, EFDA IA and FZJ Operated by the Jülich Supercomputing Centre (JSC) • Currently: 73 projects running • 20 (out of 27) EFDA associates submit jobs to HPC-FF • HPC-FF: > 50% jobs use 64 nodes (= 512 cores) or more • Jan-Apr 2011: HPC-FF utilization went up to > 90% incl. weekends Down time (maintenance) reduced by half

  11. ITER construction:Plasma diagnostics / disruption mitigation • Development of the ITER core CXRS diagnostic system • Engineering of port plug components • Spectroscopic instrumentation and atomic data • Contributions to ITER LIDAR • Development of Tritium Retention diagnostic methods • First mirror lifetime: protection and cleaning • Development of a disruption mitigation scheme

  12. Fusion Power Plants:PWI, materials, modelling, plasma control • Plasma-facing components and materials • High heat flux testing of candidate materials and PFCs • PWI with neutron-irradiated materials: erosion, fuel retention • Assessment of new materials and alternative target technologies • System studies for DEMO design • Integrated modelling for divertor optimisation • Plasma diagnostic and control • Disruption avoidance and mitigation

  13. FZJ ressources and topics HPC-FF (IA) Theory + computational engineering Objectives 1, 2+4 Plasma-wall interactionsandplasmafacingmaterialsfor ITER, W7-X + DEMO ITER construction and Fusion Power Plants Tokamak physics Objectives 1+4 W7-X construction

  14. Back-up

  15. Summary: Possible contributions by FZJ to FP8+ → ressource distribution on objectives ppy / y + Training of 24 professionals (objective 3)

  16. viewing lines for diagnostics The PWI test facility in TEXTOR • Air locks for PWI components • < 15 cm diameter (enlargement foreseen) • external heating (up to 1800K) or cooling • (down to RT) • radial movement (+- 5 cm around LCFS) • rotatable • electrical biasing of limiters • exchange time for samples <½ day • local gas injection systems • Comprehensive diagnostics • overview spectroscopy (UV-VIS-IR) • 2D imaging (Da, CII etc.), • high resolution spectroscopy • laser-induced fluorescence • 2D Thermograpy, thermocouples • colorimetry • laser desorption/ablation • edge diagnostics for ne, Te (Langmuir probes • and atomic beams) Test Limiter inserted through air lock Presently used in cooperation with Japan (TEXTOR-IEA), VR, IPPWL, Slovenia

  17. different operation modes: resonant perturbation: 16 coils mounted at the HFS: DC operation - m/n = 12/4, 6/2, 3/1 base mode - covered with graphite tiles AC operation [1-10kHz] - different penetration depth - helical set-up - B /B ~ 10% slow strike point sweeps - resonant on q=3 surface q DED Dynamic Ergodic Divertor (DED) in TEXTORflexible tool to study the impact of resonant magnetic perturbations on transport, stability and structure formation (helical divertor)

  18. Computing Facilities In Jülich Supercomputing centre (JSC): • High performance computer for fusion HPC-FF (Implementing agreement, Aug. 2009 --- July 2013) Intel-based Linux cluster 1,080 compute nodes, 8320 cores 101 Teraflop/s peak funded by EU, EFDA IA and FZJ • Currently: 73 projects running • 20 (out of 27) EFDA associates submit jobs to HPC-FF • HPC-FF: > 50% jobs use 64 nodes (= 512 cores) or more • Jan-Apr 2011: HPC-FF utilization went up to > 90% incl. weekends Down time (maintenance) reduced by half

  19. Jülich Linear Experiment for PSI studies in a Hot Cell (JULE-PSI) Specifications (realised with PSI-2 Berlin) low pressure high current arc source Heating: cathod (6.5 kW) q = 0.1 MW m-2 ne = 1017 - 1020 m-3 Te up to 20 eV (Ti~ 0.5 Te but target biasing possible) Gion = 1021 - 1023 m-2s-1 F = 1027 m-2 in 3 h (steady-state plasma) Pn up to 0.1 Pa B = 0.1 T Dflow channel ~ 5-10 cm Operation with Be and neutron irradiated materials Target and analysis station (à la MAGNUM-PSI) Linear plasma device (on the basis of PSI-2) • Lock system for hot and toxic targets • Post-mortem characterization after plasma exposure in JULE-PSI • Also allows post-mortem characterization of PFMs from nuclear devices (JET, ITER, …) + non nuclear twin outside of hot cell

  20. JUDITH 1 upgrade - High heat load tests inside Hot Cell Specifications: total power:  60 kW acceleration voltage: 120 … 150 kV max. heated area: 100 x 100 mm2 scanning frequency:  100 kHz pulse duration: 1 ms ... continuous beam rise time: 130 ms Operation with Beryllium and neutron irradiated materials

  21. JUDITH 2 – High heat load tests on large components outside Hot Cell Specifications: electron energy 30 - 60 keVbeam power: 200 kWirradiation area: 50 x 50 cm2power density: up to 10 GWm-2pulse length: 1.5 µs ... cont. beambeam scanning: digital mode Operation with Be possible Located in controlled area

  22. Ion Beam High Heat Flux Test Facility MARION Possible upgrades: Target chamber for larger targets Target manipulator for flexible position and angle Facilities for Beryllium handling

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