fzj ressources and topics
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Mem
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Association EURATOM- FZJ
CCE-Fu Workshop on European fusion roadmap for FP8 and beyond
April 13-14 IPP Garching
FZJ ressources and topics
Theory + computational engineering
Plasma-wall interactions and plasma facing materials for ITER, W7-X + DEMO
ITER construction and Fusion Power Plants
Tokamak physics
W7-X construction
Objectives 1+4
Objectives 1, 2+4
HPC-FF (IA)
Tokamak Physics:Plasma edge transport and PWI in 3D boundaries –
relevant for both tokamaks and stellarators
13th of April 2011
C - EmissionIII
m/n=12/4 m/n=6/2
C - EmissionIII
m/n=3/1
C - EmissionIII
- RMP ELM suppression / island divertor / non-axisymmetric boundary- understand transport and develop predictive modeling capabilities- benchmark experiments
TEXTOR Dynamic Ergodic Divertor
JETAUGMASTDIII-D
Theory, modelling and computational engineering Transition from 2D 3D edge modelling
(EMC3-EIRENE, B2-EIRENE, ERO)
for divertor design, addressing: Peak target heat load Plasma purity and He removal Divertor regimes (detachment)
Computational engineering for ITER design Diagnostic mirror erosion and deposition Preparing divertor codes for DEMO
CXRS port plug,CATIA design
2nd mirror
1st mirror
EIRENE code modelvia ANSIS interface(mirror lifetime assessment)
Plasma wall interactions and plasma facing materials for ITER, W7-X and DEMO
Lifetime of wall components Erosion and material migration Melt layer dynamics of metallic PFMs New concepts: development of in-situ metallic
coatings, alternative target concepts, alternative wall materials (e.g. EUROFER)
Safety Fuel retention and fuel removal, in-situ
characterization of surface layers Dust formation
PWI and edge transport in 3D structures
TEXTOR, JET ILW, JUDITH, …. MAGNUM-PSI, JULE-PSI
Plasma wall interactions and plasma facing materials for ITER, W7-X and DEMO
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
Hot Plasma Laboratory
0m 5m 10m
HML 3
HML 1
HML 2
Hot Cells
Controlled Area
Access Area
Offices
Hot Materials Lab (HML) – at present being refurbished
JULE-PSI with target exchange and analysis station
Non-nuclear twin
Be surface analysis
JUDITH 2
JUDITH 1 upgrade
JULE-PSIJULE-PSI
JUDITH 1+2JUDITH 1+2
Procurement and qualification testing
Mixed systems Be-C-W
Dust production
Retention in Be-W compounds
Transient loads
Thermal fatiguetests
Retention in n- damaged materials
SurfaceSurfacediagnosticsdiagnostics
Re-erosion of Be deposits
Erosion of n-damaged PFMs, impact of surface morphology and micro-structure
Development of modelling capabilitiesand benchmark of codes
Analysis of Be/T samples (JET, ITER)
Synergistic effectsSynergistic effects
Thermal fatigue Thermal fatigue andand thermal shockthermal shock
Thermal loads Thermal loads and and plasma exposureplasma exposure
Research Facilities In Jülich:
TEXTOR tokamak, PWI test facility, high risk experiments
PSI-2 Jülich, linear plasma device, pilot experiment for JULE-PSI
MARION, ion beam facility JUDITH 1 (Hot Cell), JUDITH 2 (Be capability),
electron beam facility JULE-PSI, JUDITH-1 upgrade in Hot Cell: ,
extended capabilities for surface analysis of toxic and neutron activated materials
TEC plasma facilities: MAGNUM-PSI, VISION-I
and JET, Wendelstein 7-X, …
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 FZJOperated 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
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
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
FZJ ressources and topics
Theory + computational engineering
Plasma-wall interactions and plasma facing materials for ITER, W7-X + DEMO
ITER construction and Fusion Power Plants
Tokamak physics
W7-X construction
Objectives 1+4
Objectives 1, 2+4
HPC-FF (IA)
BACK-UP
Summary: Possible contributions by FZJ to FP8+ → ressource distribution on objectives
13th of April 2011
W. Biel, 08.04.2011, Zahlen aus Excel Tabelle Roadmap
Objective 2012+13 2014-18 2019+20
1: ITER construction 38 33 262: Prepare ITER operation 67 67 654: Fusion Power Plants 11 16 25
0
20
40
60
80
100
120
2012+13 2014-18 2019+20
1: ITER construction
2: Prepare ITER operation
4: Fusion Power Plants
+ Training of 24 professionals (objective 3)
ppy / y
viewing lines for diagnostics
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 Limiterinserted through air lock
Presently used in cooperation with Japan (TEXTOR-IEA), VR, IPPWL, Slovenia
The PWI test facility in TEXTOR
Dynamic Ergodic Divertor (DED) in TEXTORflexible tool to study the impact of resonant magnetic perturbations on
transport, stability and structure formation (helical divertor)
C - EmissionIII
m/n=12/4 m/n=6/2
C - EmissionIII
m/n=3/1
C - EmissionIII
16 coils mounted at the HFS:
- covered with graphite tiles
- helical set-up
- resonant on q=3 surface
different operation modes:
DC operation
AC operation [1-10kHz]
slow strike point sweeps
resonant perturbation:
- m/n = 12/4, 6/2, 3/1 base mode
- different penetration depth
- B /B ~ 10%DED
Computing FacilitiesIn 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
Jülich Linear Experiment for PSI studies in a Hot Cell (JULE-PSI)
Linear plasma device (on the basis of PSI-2)
Target and analysis station (à la MAGNUM-PSI)
Specifications (realisedwith PSI-2 Berlin)low pressure high currentarc sourceHeating: 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)
ion = 1021 - 1023 m-2s-1
F = 1027 m-2 in 3 h (steady-state plasma)
Pn up to 0.1 PaB = 0.1 T
flow channel ~ 5-10 cm
Operation with Be and neutron irradiated materials
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+ non nuclear twin outside of hot cell
18th of June 2009
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 s
Operation with Beryllium andneutron irradiated materials
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 cm2
power density: up to 10 GWm-2
pulse length: 1.5 µs ... cont. beambeam scanning: digital mode
Operation with Be possible
Located in controlled area
Ion Beam High Heat Flux Test Facility MARION
Total beam power 70 kW to 6.0 MW (I = 100 A, E = 60 keV)
Beam area (cm2) 1300 (32 cm wide x 40.5 cm high)
Sample holder 15- x 10-cm sample size, actively or passively cooled
Particle type H+, Ho, He
Maximum particle energy 10 to 60 keV with profilePower density (MW/m2) 1.4 to 120
Pulse length 10 ms to 15 s (≈ minutes with reduced power)
Repetition rate (min) 1 to 5 (depending on power and pulse length)
Rise time (ms) 2 to 200 (adjustable)
Steady state Operation with reduced power of 600 kW (power density of 1.3 kW/cm2)
Possible upgrades:
Target chamber for larger targets
Target manipulator
for flexible position and angle
Facilities for Beryllium handling
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