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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