detlev reiter - iaea, amd unit page · detlev reiter. forschungszentrum jülich gmbh, institut für...
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Forschungszentrum Jülichin der Helmholtz-Gemeinschaft
Detlev
ReiterForschungszentrum Jülich GmbH, Institut für Energieforschung-4
52425 Jülich, Germany
Can we tend the fire?
Joint ICTP-IAEA Workshop on Atomic and Molecular Data for Fusion, Trieste 20-30 April 2009
Three lectures course on plasma surface interaction and edge physics
III.) WHY ? Understanding plasma surface interaction
Thanks to: V. Kotov, P. Börner
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TEXTORT.Supra
NOW 2015-2025 2025 ……
PrototypicalFusion Reactor
The vision……
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Computational Science Workflow “Waterfall Model” (1960-th…)
(the dream of code development managers)
1)
Requirement (e.g.: integrated fusion code for ITER)
2) Planning and design
3) Code (Programming)
4) Test
5) Run
Computational Science and Engineering is moving from “few effects”
codes developed by small teams (1-3 scientists) to “many effect codes”
codes developed by larger teams (10-20 or more).
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The process is:•Very complex•Risky•Takes Long
The reality in large scale code development projects
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IntegratedModellingTheory
Support
Gateway
Code Repository Data Servers
Associations’Computers& Clusters
AssociationsIFERC
(B.A. 2012) …EU-Fusion-HPC(2008)
EU-Super Computers(“PRACE”
2010)
EUFORIA
GRID Technology
Courtesy: A.Becoulet
EU ITM Task Force
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The EU 100 TF HPC-FF will start operation in spring 2009
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Institute for Advanced Simulation Jülich
Supercomputing Centre
(JSC)
Supercomputer for Fusion Science @ Jülich
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Present Supercomputer Environment FZJ
Jülich
Supercomputing Centre (JSC) 8
General Purpose
Supercomputer High Scalable
Supercomputer
On-line
Storage, 1 PByte Robot Silo, 4 PByte
BlueGene/P, 223 TFlop/s
No. 2 in Top500-List
Nov. 2007
JUMP, 1312 processor Regatta p690+,
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Supercomputer Environment by End of 2008
Jülich
Supercomputing Centre (JSC) 9
Jülich‘s
next General Purpose Supercomputerto be installed in 2008
Storage
Environment
BlueGene/P, 223 TFlop/s2 GByte per node
•
2048 nodes @ 8 cores•
24 GByte
per node•
Intel NEHALEM•
Network: QSnetIII•
Peak Performance about 200 TFlop/s
•
1000 nodes @ 8 cores
of same architecture
•
Estimated Peak Performance
about 100 TFlop/s
Supercomputer forFusion Science
Flexible swapping of resources
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Pfus ≈
540-600 MW⇒ He flux⇒ PSOL ≈86-120 MW
ns ≈(2-4)·1019
m-3
Sinj ≤
10·1022
s-1
Spump ≤
200 Pa·m-3/s
Zeff ≤1.6CHe ≤6%qpk ≤10 MW/m2
Provide
sufficient
convection
without
accumulating
tritiumand with
sufficiently
long
divertor lifetime
(availability).
Engineering parameter : Spuff ~ (1…13)·1022
s-1
!
?
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ELECTRON TRANSIT
ISLAND GROWTH CURRENT DIFFUSION
Single frequency and prescribed plasma background
RF Codes wave-heating and current-drive
SEC.10-8 10410210010-210-410-6Ωce
-1
10-10ωLH
-1 τAΩci-1
SAWTOOTH CRASH
TURBULENCE
ENERGY CONFINEMENT
Neglect displacement current, average over gyroangle, (some) with electrons
Gyrokinetics
Codes
turbulent transport
Neglect displacement current, integrate over velocity space, average over surfaces, neglect ion & electron inertiaTransport Codes
discharge time-scale
Typical Time Scales in a next step experiment with B = 10 T, R = 2 m, ne
= 1014
cm-3, T = 10 keV
Neglect displacement current, integrate over velocity space, neglect electron inertia
Extended MHD Codes
device scale stability
Fusion Simulation Project Vol.2, FESAC ISOFS Subcommittee
Final Report, Dec. 2002
core
plasma
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ELECTRON TRANSIT
ISLAND GROWTH CURRENT DIFFUSION
SEC.10-8 10410210010-210-410-6Ωce
-1
10-10ωLH
-1 τAΩci-1
SAWTOOTH CRASH
TURBULENCE
ENERGY CONFINEMENT
Typical Time Scales in a next step experiment with B = 10 T, R = 2 m, ne
= 1014
cm-3, T = 10 keV
Neglect displacement current, average over gyroangle, (some) with electrons
Gyrokinetics
Codes
turbulent transport
Neglect displacement current, integrate over velocity space, average over surfaces, neglect ion & electron inertiaCore Transport Codes
discharge time-scale
Atomic & molecular processes
Neutral particle codes, kinetic imp.transport codesplasma chemistry
Ion drift wavesTransients (ELMs)
ITM
Edge turbulence
Parallel dynamics:Ion transit, Ion collisionsParallel sound waveDitto, electrons
2D transport codes
core
plasmaedge plasma Well separated: transport –
turbulence: good !
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EDGE plasma
• No clearly separated timescales, i.e. no natural separation into reduced sub-models.
• Far more challenging than at inito
core plasma transport:There turbulence and transport time scales are clearly separable.
• Similar situation: Computational material and PWI science
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Thanks
to: R.Schneider, IPP Greifswald
Material and PSI time-
and spatial
scales
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Generic kinetic (transport) equation
(L. Boltzmann, ~1870)
( ) ( ) ( ) ( ) ( )Ω−Ω=+Ω∇⋅Ω+∂
Ω∂ rrrrr
,,,, EfEvESForcesEfvt
Efaσ
( ) ( ) ( ) ( )[ ]∫∫ ΩΩ′⋅Ω′→−Ω′′Ω⋅Ω′→′′Ω′′+∞
π
σσ40
,,,,rrrrrrr
EfEEvEfEEvdEd ss
•for particles travelling in a background (plasma)between collisions•with (ions)
or without (neutrals)
forces (Lorentz)
acting on
them between collisions
),,( tvrf rrBasic dependent quantity: distribution function
Free flight External source Absorption
Collisions, boundary conditions
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Characteristics (=Trajectories) of kinetic transport equationhere: MAST, Culham, UK
Here: mainly H, H2
, Cx
Hy
neutrals
MAST: Geometry and exp. plasma data provided by S. Lisgo, UKAEA, 2007
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EIRENE kinetic transport code (www.eirene.de): gyro averaged ion kinetic up to edge-core interface
MAST: Geometry and exp. plasma data provided by S. Lisgo, UKAEA
Here: C, C+, C2+, …
atomic carbon neutrals and ions
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Continuity
equation
for
ions
and electrons
Momentum
balance
for
ions
and electrons
Energy balances
for
ions
and electrons
( )∂∂t
n n V Si i i ni+ ∇ ⋅ =r r ( )∂
∂tn n V Se e e ne
+ ∇ ⋅ =r r
( ) ( ) ( )iiVmiiiiiiiiiiiii SRBVEenZpVVnmVnm
tr
rrrrrtrrrrrr++×++∏⋅∇−∇−=⋅∇+
∂∂
( )−∇ − + × + =r r r r r
p en E V B Re e e e 0
( ) iEeiiiiiiiii
iiiii
iiii SQVREZenqVVV
nmTnV
nmTn
t+−⋅−=⎥
⎦
⎤⎢⎣
⎡+⋅∏+⎟
⎠⎞
⎜⎝⎛ +⋅∇+⎟
⎠⎞
⎜⎝⎛ +
rrrrrtrrrr22
225
223
∂∂
∂∂t
n T n T V q en E V R V Q Se e e e e e e e i ei Ee3
252
⎛⎝⎜
⎞⎠⎟ + ∇ ⋅ +⎛
⎝⎜⎞⎠⎟ = − ⋅ + ⋅ + +
r r r r r r r
Collisionality plasma fluid approximationmulti-ion fluid (α ion species, Tα = Ti, and electrons)multi-species Boltzmann eq. for neutrals (n neutral species)Braginskii, Reviews of Plasma Physics, 1965
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Momentum
balance
for
ions
and electrons(Navier
Stokes
„Braginskii“
equations)
( ) ( ) ( )iiVmiiiiiiiiiiiii SRBVEenZpVVnmVnm
tr
rrrrrtrrrrrr++×++∏⋅∇−∇−=⋅∇+
∂∂
⊥+⊥∂−⊥∂−= ⎟⎟⎠
⎞⎜⎜⎝
⎛⎟⎟⎠
⎞⎜⎜⎝
⎛
⊥⊥⊥ Vph
Dnh
Dv pn αα
αα
α lnln
In edge codes often used only for αvװ
the flow parallel to B-field
The cross field momentum balance is replaced by diffusion-convection ansatz:
with
ad hoc (anomalous?)
D⊥
,V⊥
κ⊥
, η⊥,
e.g. Strahl code,…..
ASIDE
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Fusion devices
TEXTOR (R=1.75 m), Jülich, GER
JET (R=2.96 m), Oxford, UK
ITER (R=6.2 m), Cadarache, FRA
joint: EU joint: world-wide
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Fusion devices: typical transport code runtime
TEXTOR (R=1.75 m), Jülich, GER
JET (R=2.96 m), Oxford, UK
ITER (R=6.2 m), Cadarache, FRA
joint: EU joint: world-wide
1 day
1-2 weeks 3 months
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Why become transport codes so slow for ITER sized machines?
(for same model, same equations, same grid size)
Because of more important plasma chemistry
(increased non-linearity, non-locality, in sources).
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Continuity
equation
for
ions
and electrons
Momentum
balance
for
ions
and electrons
Energy balances
for
ions
and electrons
Fluid
equations
for
charged
particles
( )∂∂t
n n V Si i i ni+ ∇ ⋅ =r r
( ) ( ) ( )iiVmiiiiiiiiiiiii SRBVEenZpVVnmVnm
tr
rrrrrtrrrrrr++×++∏⋅∇−∇−=⋅∇+
∂∂
( )−∇ − + × + =r r r r r
p en E V B Re e e e 0
( ) iEeiiiiiiiii
iiiii
iiii SQVREZenqVVV
nmTnV
nmTn
t+−⋅−=⎥
⎦
⎤⎢⎣
⎡+⋅∏+⎟
⎠⎞
⎜⎝⎛ +⋅∇+⎟
⎠⎞
⎜⎝⎛ +
rrrrrtrrrr22
225
223
∂∂
∂∂t
n T n T V q en E V R V Q Se e e e e e e e i ei Ee3
252
⎛⎝⎜
⎞⎠⎟ + ∇ ⋅ +⎛
⎝⎜⎞⎠⎟ = − ⋅ + ⋅ + +
r r r r r r r
System of PDGL’s
with locally increasing dominating sources:“diffusion-reaction-equations”
rather than pure CFD
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Kinetic (transport) equation, one for each species( ) ( ) ForcesEfv
tEf
+Ω∇⋅Ω+∂
Ω∂ rrr
,,
( ) ( ) ( ) ( )[ ]∫∫ ΩΩ′⋅Ω′→−Ω′′Ω⋅Ω′→′′Ω′′+∞
π
σσ40
,,,,rrrrrrr
EfEEvEfEEvdEd ss
Transport External source Absorption
Collisions
( ) ( ) ( )Ω−Ω=rr
,, EfEvES aσ( )
τf
tEf
+∂
Ω∂r
,
System then becomes analogous to:
SfMf rrtr
+=∂∂
tfor those fi
, for which the transport has been removed from kinetic equation
Separating time scales in plasma chemistry:
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CR Models in Transport Codes (“bundled states”)
1) System of N kinetic (or fluid) equations (PDGL, IGL)
2) select M species, remove transport termand explicit time derivative(Interpretation: their lifetime is short compared to
transport time)
3) System reduced to N –
M transport equationsplus one linear algebraic system (CR Model), oforder M
The M states are in quasi steady state with the N –
M transported species.
CR models are QSS models(this is also known as “bundled state model”)
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Characteristics (=Trajectories) of kinetic transport equation here: MAST, UKAEA Culham, UK
Here: mainly H, H2
, Cx
Hy
neutrals
MAST: Geometry and exp. plasma data provided by S. Lisgo, UKAEA, 2007
QSS (condensed): H2+, and all excited states
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EXAMPLECollision-radiative
model (CR) [K. Sawada, T. Fujimoto, 1995] for H,p,H2
,H2+ (and H*, H2
*, H2+* as fast QSS-species)
C: electronic
excitation; F: electronic
de-excitation;A: radiative decay;R: recombination; S: ionization; D: dissociation.
+++
<<><
++++
−
−−−==> ∑∑∑∑
222211
0 1
HepHHepHepep
pep
pqppq
pqpepq
pqpepq
pqqeqp
nnDnnDnnRnnC
nnS
nAnnFnnCnnCdtpdn
Similar for nH2
*, nH2+*, total: ~ 100 species, N –
M = 4
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How to select M “fast”
states
H2
: are H2
(v) “metastable”
or QSS speciesIn Cx
Hy
brake-up: which are QSS?
A sound mathematical procedure (from combustion and flame science):The Intrinsic Low Dimension Manifold (ILDM) technique.(but: very cumbersome to implement in transport codes)Based on spectral analysis of reaction system.
See :Dauwe, Tytgadt, Reiter: “Automatic reduction of the hydrocarbon reaction Mechanisms in fusion edge plasmas, JUEL-4299, Nov. 2006, ISSN 0944-2952and: www.eirene.de/recentreports
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Example: MAST (UK)
Plasma temperature in KCourtesy: S. Lisgo
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Consistent Plasma-Gas-Radiation fields in MAST edge
Tene nD nD29.5×1018 m-3 max 30 eV max 0.6×1018 m-3 max 0.6×1019 m-3 max
Tene nD nD29.5×1018 m-3 max 30 eV max 0.6×1018 m-3 max 0.6×1019 m-3 max
Plasma flow (experiment + OSMModelling)
Gas flow (atomic and molecular)EIRENE
Courtesy: S.Lisgo
et al., MAST Team, EPS 2007
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INVERTED Dα
IMAGE
OSM-Eirene
UPPER DIVERTORDα
IMAGE
Courtesy: S.Lisgo
et al., MAST Team, EPS 2007
Spectroscopy OSM transport modelling CR plasma chemistry modellingQuantitative comparison experimental validation of tokamak edge chemistry
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TransportTransport--Simulations for ITERSimulations for ITER
Plasma flow fieldin ITER Divertor
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Numerical tool for the edge plasma science:B2-EIRENE code package (FZJ-ITER)
B2: a 2D multi species (D+, He+,++, C1+..6+,…) plasma fluid code
EIRENE: a
Monte-Carlo neutral particle, trace ion and radiation transport code.
Plasma flowParameters
Source terms (Particle, Momentum, Energy)
Computational Grid
Self-consistent description of the magnetized plasma, and neutral particles produced due to surface and volume recombination and sputtering
see www.eirene.de
Reiter, D., et al., Fusion Science and Technology 47 (2005) 172.
CR codes:HYDKIN
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ITER, B2-EIRENE simulation, fully detached, Te
field
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ITER, B2-EIRENE simulation, detached, ne
field
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ITER, B2-EIRENE simulation, detached, nA
field
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ITER, B2-EIRENE simulation, detached, nH2
field
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PPFR
: average neutral pressure in Private Flux Region
ITER divertor engineering parameter: target heat flux
vs. divertor gas pressure
1996 (ITER physics basis1999)
2003, neutral -
neutral collisions
….+ molecular kinetics (D2
(v)+D+, MAR) 2005, + photon opacity
Consequences
for
ITER design
(B2-EIRENE): shift
towards
higher
divertor
gas pressure
to maintain
a
given
peak
heat
flux
(Kotov
et al., CPP, July
2006)
ITER design
review 2007-2008:
“Dome“
re-design now
considered
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ITER Divertor design is based upon “detachment”
Detachment is a chemically complex plasma state: “unknown territory”
in fusion,
but well known in low temperature plasma physics
-
gas-plasma friction,
-
recombining plasmas,
-
plasma cooling (radiation)
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Current hypothesis: in the “detached state”
is the divertor dynamics
and chemistry is controlled by “Collisionality”(inv. Knudsen number)
Estimate “Collisionality”: ne
R-ne
-Divertor Plasma density (×1020 m-3)-R-
Major Radius (m)
Alcator
C-Mod (MIT)10 times smaller than ITERsimilar shapehigher density
Factor
11away Factor
6 away
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Shot: 990429019, at 950ms, <ne
>=1.5 1020, IP
=0.8 MA, Btor
=5.4 TOSM reconstruction (Lisgo
et al., 2004)
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Dγ
(from D, D2
, D+,D2+):
Profile matched, but high by factor 2Calibration? Atomic Data? Plasma reconstruction?
Results very sensitive eg. to Te
profile
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E [eV]H2
+
E,F CB
a c
b
v=3v=2v=1v=0
···
Singlet Triplet system
10
0
2
4
6
8
12
14
16
n=2
n=3
H2
v=14
compiled
1997
H2
molecule, status
in presentdivertor code
35
30
25
20
15
10
5
0
Pote
ntia
l En
ergy
(eV
)
43210Internuclear Distance (A)
H2
X1Σg+
b3Σu+
X2Σg+
H2+
n=3n=4
E,F1Σg+
a3Σg+
B1Σu+
C1Πu
c3Πu
H++ H
H + H
compiled
2005
More
complete
models
available,still need
to be
integrated
13.6 eVResonance
! H*+H
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Critical for particle throughput (convection):
Neutral Plenum Pressure
Exp: 25 mTorrCalc 2D (2000) 3 mTorrCalc 2D (2003) 27 mTorr(better A&M data,better Plasma data,better codes)
Very good match: code -
experimentBut:Is there further edge physics that we are sure must be operative?
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Additional leakage pathways:
2D 3D(see later)
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3D Neutral Gas, A&M and PSI Modelling
3D divertor structures (toroidal gap and gussets, bypass
and poloidal
gap)
strong toroidal variations in the divertor neutral pressure
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Ionization by electron impact on neutral gas
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Radiation transfer: opacity of Ly-lines(though completely elementary, has long remained unnoticed in edge modelling)
hν+H(1) H*, H*+e H+ 2e (additional path for ionization in dense, low Te
divertors)
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Neutral Pressure
Exp: 25 mTorrCalc 2D (2000) 3 mTorrCalc 2D (2003) 27 mTorr(better A&M data,better Plasma data)
Ly-opacity: 17 mTorr3D: 11 mTorr
However
Model validation in the presence of many free parameters:
include ALL edge physics that we are sure must be operative even while our capability to confirm these directly remains limited
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High Intensity Discharge Lamps
CDM-75 WShop-LightingMaterial:PCA
D2-36 WAutomotive
Material:Quartz
B2B2--EIRENEEIRENE
4 m
m4 m
FIDAPFIDAP--EIRENEEIRENE
Radiation
transfer
module: verification
and validation
using
HID lamps
ITERITER
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• Extending
edge models
towards
predictive
quality
isa theoretical
and experimental task
• Going
from
2D CFD to 3D CFD is
a computational
physics
task
0 3D recycling, reaction-diffusion
problems: in hand
1: smooth
particle
hydrodynamics+ random
walks
(ITER, W7X, LHD)
2
Edge ergodization
(TEXTOR-DED, DIIID: C-Coils, ELM-mitigation)
2D 3D
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Interior view of Tore Supra
Tore Supra
Full toroidal limiter CIEL
Θ poloidal direction
ϕ
θ
φ
toroidal direction
machine axis
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Tore Supra heat, particle flux deposition is strongly influenced by magnetic field ripple (~7%)
R Mitteau
et al J Nucl
Mater 2001.
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Large Helical Device (LHD), Toki, Japan
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Te ne
nA nM
3D LHD Plasma Edge Simulation (Kobayashi, Reiter, Feng, 2005)
Prediction: high source
upstream, high flow
speed, low
T near
target
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TEXTOR-DED: smooth
particle
hydrodynamicsMonte Carlo for
non convective
terms
interpolated
cell
mapping
for
stochasticity
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Conclusions/Outlook
Similar to previous steps: progress to ITER is based mainly on experimental and empirical extrapolation
guided by theory and aided by modellingPresent goal:
include all of edge physics that we are sure must be operative (opacity, A&M physics, surface processes, drifts…, even while our capability do confirm these directly remains limited.
Present upgrading: -
low temperature plasma chemistry
-
consistent wall models-
drifts and electrical currents in the edge
- 2D 3D-
coupling to first principle edge turbulence codes
-
code integration: Core-
ETB –
edge (ELM modelling)
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Summary: Edge Theory
and Modelling
Compare with aircraft aerodynamics
Where are we? A reality check
Things in Common:
•Both
use
fluid
models/codes
as primary
analysis
tool
•In both
cases
one
can
get
fairly
far with
2D (ITER design) but
in the
end: 3D is
needed
•Both
involve
a powerful
controlling
fluid-solid
interaction/interface
•Both
involve
turbulence
in an important
way
•Both
are
applied
sciences: What, Why, How
(how
can
we
make
this
application
work?)
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Summary: Edge Theory
and Modelling
Compare with aircraft aerodynamics
Where are we? A reality check
The
differences:•Aero: involves
2 states
of matter. The
Edge: minimum
3, sometimes
all 4•Aero: involves
no B or
E fields, no currents, Maxw. Eq. play
no role.Edge: Maxwells eqs. as important
as fluid
eqs. •Sub-sonic
aero: largely
incompressible
flow. Our
fluid
is
compressible•Aero: one
fluid. We: many
fluids
(electrons, ions, impurities…)•Aero: no exchange
of matter. For us: the
exchanges
are
dominating•Aero: some
unsteady
effects, but
no equivalent
to our
powerful
effects: ELMs…•Aero: 2D flow
field
can
be
studied
in small, cheep, wind tunnels,done
1000‘s of times
over
100 yearsWe
need
2D (3D) fluid
field
for
all fluids, around
the
entire
edge
(when? cost?)
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Summary: Edge Theory
and Modelling
Where are we? A reality check
Computational aircraft aerodynamics is still an active field of research.
If computational edge plasma science would be “largely in hand”,it would be a miracle.
A major computational edge plasma science effort is needed, in order to avoid major code failures in the ITER design and operation
Edge plasma: orders
of magnitude
more
complex, orders
of magnitude
less
R&D
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The JET divertor
design philosophy
Michael Pick
has used to describe the design of the JET divertor:
"The only way to do research is to tell the complete truth. And the truth is that research is often based partially on intuition, which is a perfectly acceptable basis for research in the face of a lack of evidence and verified predictive models.We built the divertor based on what we thought would be a reasonable solution, based on simple extrapolation, models and intuition, leaving open the possiblities to change."
Still true for ITER, despite significant progress inedge plasma science and in predictive quality of models
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• One and a half decade ago we lacked a credible solution to the divertor
problem.
•
With the discovery of the cold,detached, radiating divertor
inthe 1990s, we now have (themakings of) a divertor
solutionfor high power magneticconfinement devices.
We
now
have
enough
understanding
of „WHAT“(JET, Tore-Supra, D-IIID, ASDEX, LHD, W7AS,…..)to proceed
with
the
„HOW“
(to build
ITER,…)Very
little
on the
„WHY“
question
still, see
lecture
III But
we
are
ready
to go:
Bring on ITER!
Compare to similar situationafter first flight ofWright brothers
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The End
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Reserve slides
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Bϕ
Bx∇B
Er
xB, ∇pxB
Ballooning
Pfirsch-
SchlüterDivertor
sink
Eθ
xB
Simplified –
flow components in poloidal
plane only
Poloidal
Parallel
Motivation Motivation –– understanding SOL flowsunderstanding SOL flows
FWD Bϕ
Bϕ
Bx∇BREV Bϕ
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The Impurity Transport Code ERO
IV.) Applications of ERO
The ERO webpage – still under development …
(http://www.efda-taskforce-pwi.org/ero/