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Forschungszentrum Jülich in der Helmholtz-Gemeinschaft
Detlev Reiter
Forschungszentrum Jülich GmbH, Institute for Energy and Climate Research
52425 Jülich, Germany
ICTP-IAEA Joint Workshop on Fusion Plasma Modelling using Atomic Molecular Data, Trieste 23-27 Jan. 2012
Introduction to edge plasma modelling
Forschungszentrum Jülich in der Helmholtz-Gemeinschaft
Introduction to edge plasma modelling
Like in any applied science: Three questions
I.) WHAT : …happens? A &M & plasma-wall interaction processes
II.) HOW : …can we make the application work? ITER
III.) WHY : understanding the edge plasma,
using A&M&S data in edge plasma modelling
Outline of course:
See other lectures
Some unfinished business
www.eirene.de
www.hydkin.de
JET, MARK-I,
density ramp-up
-ohmic
-no imp. injection
-simply: D2-puff
Full detachment is a problem
JET, A. Huber, et al.
[12]
Detachment which is too “strong” (particle flux reduced across the whole target) is often associated with zones of high radiation in the X-point region and confined plasma (MARFE)
MARFE formation can drive a transition from H to L-mode (H-mode density limit) or disruption
MARFE physics still not well understood
Limit detachment to regions of highest power flux (where it is needed most).
Maintain remainder of SOL in high recycling (attached)
A few ways to arrange that this happens more readily:
Divertor closure Target orientation Impurity seeding
Courtesy: R. Pitts
Divertor closure
Increased closure significantly improves divertor neutral pressure increased neutral density (nn), promoting earlier detachment
Closing “bypass” leaks important for increasing nn
Divertor closure also promotes helium compression and exhaust – very important for ITER and reactors
JET, R. D. Monk, et al.
[13]
Courtesy: R. Pitts
Target orientation
Parallel heat fluxes significantly reduced for vertical cf. horizontal targets
Underlying effect is preferential reflection of recycled deuterium neutrals towards the separatrix
Neutrals into hotter plasma
near separatrix
Increased ionisation near sep.
Higher nt, lower Tt
Higher CX losses
AUG, A. Kallenbach, et al.
Neutrals into cooler, less
dense plasma
Pressure loss q||
Sepa
ratrix
Courtesy: R. Pitts
Impurity seeding
JET, G. F. Matthews et al.
Unfuelled
(attached)
Strong D2 puff
(weak detachment)
Strong D2 +N2 puff
(stronger detachm.)
Strong impurity seeding also reduces ELM size but
high price can be paid in confinement
ITER divertor designed to achieve partial detachment
ITER Divertor DDD 17, Case 489 (SOLPS4.2 runs by A.
Kukushkin)
Deep V-shaped divertor, vertical, inclined targets
Dome separating inner and outer targets – also helpful for
diagnostics, neutron shielding and reducing neutral reflux to
the core
Inner strike pt.
Pow
er lo
ad
(W
m-2)
Outer strike pt.
Courtesy: R. Pitts
Candle, on earth
Convection, driven by buoyancy
(i.e. gravity)
Only Diffusion (no convection)
Candle, under mircogravity
(only small,
dim burn,
at best)
Fresh air
Us
ed
air
e.g.: parabola flight,
g ≈ 0
Can we hope that magnetic confinement core plasma physics progress
will mitigate plasma-surface problems ?
Divertor exhaust
Apart from power handling, primary function of
divertor is to deal with He from fusion reactions
compress D, T, and He exhaust as much as
possible for efficient pumping (and therefore also
good density control).
To cryopumps
Critical criterion for an ITER burning plasma
is that He is removed fast enough such that:
is satisfied.
is the global helium particle residence
time – a function of tp, the He neutral
density in the divertor and the pumping
speed (conductance) .
Helium
enrichment:
is the ratio of He concentration in the
divertor compared to the main plasma.
105/*
, EHep tt
plasma
pump
e
plasma
He
pump
D
pump
HeHe
C
C
nn
nn
/
2/ 2
*
,Hepte.g. ITER: He prod. rate ~21020s-1
Max. divertor pumping speed
~200 Pa m3s-1 ~ 11023 He atom s-1
Cpump ~ 210-3 = 0.2%
Typical acceptable He conc. in the
core: ~4% He = 0.2/4 = 0.05 is
minimum required. The values of
and required for ITER have
been achieved experimentally
*
,Hept He
Courtesy: R. Pitts
Opacity in Fusion edge plasmas?
Only for resonance lines: Lyman-series
12
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
The Photon mean free path
]cm[n
T108.1n
T104.5mfp
a
13
1
a
2/1
0
9
0
Ly- Doppler Profile (5 eV) 10 cm
30 cm
50 cm mfp for na=1013
eV
At line centre:
for Lyman lines
13
Experimental observations
Terry et al, PoP 5,5 (1998) 1759:
Alcator C-Mod:
clear evidence for strong opacity effects
Ratio: Lyman- /Balmer-: proof of opacity
ne: low
ne: high
Lyγ
remains opt. thin
14
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
Norm
alis
ed a
bsorp
tion
- an
d e
mis
sion l
ines
hap
es
[eV]
H D T
1 eV
10 eV
Lyman- Voigt-Lineshapes mfp
1~ (Photon mean-free-path)-1
15
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
April 29th 2002
Escape factors: zero dimensional corrections
to account for radiation trapping
Line escape factors:
for line of sight spectroscopy
(provided also by EIRENE, with zero statistical noise)
Population escape factors:
modify ionisation-recombination balance.
Important for dynamics in detached plasmas
E
G
rj
ddrIrr line
P
1)(4
),()(1)( 4
ikPik ArA )(
16
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
April 29th 2002
Comparison: ADAS vs. EIRENE escape factors
long cylinder case, homogeneous plasma
pure Doppler broadening (kT = 1 eV)
EIRENE population escape factor evaluation
(Optical thickness)
17
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
April 29th 2002
Comparison of D atom profiles
before after
18
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
April 29th 2002
Lyman- photon density (log scale), after iteration
19
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
April 29th 2002
population escape factor
A.S. Kukushkin, 12th PET, Rostov, Russia, 2nd September 2009 (ITER_D_2NJZH5) Page 20
A.Kukushkin, PET 2009 Episode 11: radiation transport
Partial detachment, high nneut Lyman series radiation MFP < 1 cm strong increase of ionisation, change of ionisation/recombination balance
Radiation transport in Eirene: several Ly series, photons like neutrals
SOLPS calculations: no effect on qpk and nHe, although plasma parameters in divertor change strongly
Reason: stronger ionisation in cold region increase of n increase of recombination (Sion n2; Srec n3)
Important for diagnostics, less for performance
don’t trust simple models!
dome, n-n D+He add Lyman trans.
0.001
0.01
2 4 6 8 10
30
5_
C0
_n
t_ly
_z0
8_
1
nHe_sep
[1020m-3]
pDT
[Pa]
1
10
2 4 6 8 10
30
5_
C0
_n
t_ly
_z1
1_
1
qpk
[MW/m2]
pDT
[Pa]
Why do edge codes take forever to
converge ?
wall
plasma core
target
target
10 m
10 cm
recycling
Major radius = 2-6 m
(distance to torus center)
A simple model, to illustrate the numerical challenge
B
Plasma flow
Gas flow
The often hidden challenge: code convergence, iterating on noise ??,…..
Code performance: Plasma Flow alone, B2, serial
B2, without EIRENE
1.00E-11
1.00E-09
1.00E-07
1.00E-05
1.00E-03
1.00E-01
1.00E+01
1.00E+03
1.00E+05
0 500 1000 1500 2000 2500 3000
no. of timesteps
resid
ual
(1/s
ec)
resee
resei
resco
resmo
Expected uncritical behavior, errors reduced exponentially to machine
precision.
Numerical Convergence errors (residuals)
during CFD run, vs. timestep Part. Balance (D+)
En. Bal (D+)
En. Bal. (electrons)
Moment. Balance
(Navier Stokes)
convergence behaviour of the coupled
B2-EIRENE codesystem (1)
coupled B2-EIRENE calculation,
recycling coefficient R=0.3
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
0 200 400 600 800 1000
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
B2 with analytic recycling model
(without EIRENE),
recycling coefficient R=0.3
1.E-03
1.E-02
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
0 200 400 600 800 1000
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
B2, R=0.3 B2-EIRENE, R=0.3
This is what we want (Analytic recycling model=
unrealistically simplified Boltzmann eq.)
And this is what we get (full Boltzmann eq., Monte Carlo)
Numerical Convergence errors (residuals)
during CFD run, vs. timestep
Code performance: serial, B2-EIRENE, ITER test case, Linux PC 3.4 GHz
(typical for all “micro macro models” in computational science)
0.01
0.1
1
10
100
1000
10000
0 500 1000 1500 2000
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
3h 15h 150h =
6.25 days
10s per EIRENE call
100s per
EIRENE call 1000s per
EIRENE call
Convergence limited by statistical Monte Carlo noise.
In order to reduce error by factor 10, runtime
(or number of processors) has to be increased by factor 100
What is a measure for: Performance ? Convergence ?
Comp. Sci + appl. Math.
convergence behaviour of the coupled
B2-EIRENE codesystem (2)
coupled B2-EIRENE calculation,
recycling coefficient R=0.99
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
0 500 1000 1500
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
coupled B2-EIRENE calculation,
recycling coefficient R=0.3
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
1.E+05
0 500 1000 1500
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
10s per EIRENE call
100s per
EIRENE call
3 h
15 h
low recycling high recycling
Convergence in given CPU-time depends
on level of recycling (= vacuum pumping speed)
3 h
15 h
convergence behaviour of the coupled
B2-EIRENE codesystem (3)
Total particle content
Recycling coefficient R=0.3
5.2E+20
5.3E+20
5.4E+20
5.5E+20
0 500 1000 1500
no. of timesteps
part
icle
co
nte
nt
(#/m
**3)
Total particle content
Recycling coefficient R=0.99
5.2E+20
6.2E+20
7.2E+20
8.2E+20
0 500 1000 1500
no. of timesteps
part
icle
co
nte
nt
(#/c
m**
3)
Total energy content
Recycling coefficient R=0.3
1.5E+04
2.0E+04
2.5E+04
3.0E+04
3.5E+04
4.0E+04
4.5E+04
5.0E+04
0 500 1000 1500
no. of timestepsen
erg
y c
on
ten
t
electron energy
ion energy
Total energy content
Recycling coefficient R=0.99
1.5E+04
2.0E+04
2.5E+04
3.0E+04
3.5E+04
4.0E+04
4.5E+04
5.0E+04
0 500 1000 1500
no. of timesteps
en
erg
y c
on
ten
t
electron energy
ion energy
low recycling
R=0.3
high
recycling
R=0.99
“Is is enough to see one lion to know you are in a desert”
Correlation sampling and convergence of B2-EIRENE
Here: correlation produced by simple manipulation of random
number generator
coupled B2-EIRENE calculation,
recycling coefficient R=0.3
with correlation sampling
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
0 200 400 600 800 1000
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
coupled B2-EIRENE calculation,
recycling coefficient R=0.3
without correlation sampling
1.E-01
1.E+00
1.E+01
1.E+02
1.E+03
1.E+04
0 200 400 600 800 1000
no. of timesteps
resid
ual (1
/sec)
resee resei resco resmo
Without correlation sampling cpu time has to be increased by a factor 100 to reach the
same convergence level !
How much correlation ? Damping of noise, without freezing error from early iterations.
Recent Progress and Challenges
Going from 2D 3D…..
30
Trilateral Euregio Cluster
TEC
Inst itut für PlasmaphysikAssoziat ion EURATOM-Forschungszentrum Jülich
The experimental experience:
to stir a liquid
Creating turbulent (chaotic) flow
can largely increase heat transfer
(avoid local overheating)
The theory:
“passive scalar transport in chaotic force fields”
Not yet understood on a quantitative level
very active modern research field of
•theoretical physics
•large scale numerical computing.
Avoid excessive heat loads by stirring (magnetically) the plasma?
TEXTOR-DED: Dynamic Ergodic Divertor
13th of April 2011
Dynamic Ergodic Divertor (DED) in TEXTOR
flexible 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 q
D.Harting, D.Reiter, JUEL-4173, May 2005
Field line tracing- 3D plasma fluid –neutral gas kinetic modeling
Partially ergodic 3D magnetic field topology
3D edge codes also Monte Carlo for plasma flow fields (EMC3)
TEXTOR-DED B-Field (R-Z) TEXTOR-DED B-Field (r-θ)
“Particle” methods:
also well established in fluid dynamics
• Lagrangian method Eulerian (grid based) method
• Advantages:
• + concentrate “particle” in the interesting region
• + Convective transport essentially without numerical dissipation in arbitrarily complex geometry
• Disadvantages:
• - Non-convective terms (collisions, diffusion)
• Solution: Monte Carlo fluid (random walk model)
• in Fusion: this is the concept of E3D and EMC3-EIRENE codes (IPP Greifswald)
• - looses accuracy in region of interfacial boundaries
EMC3-EIRENE: FZJ: mainly tokamak applications (RMPs)
Example: DIII-D ELM mitigation scenarios
Goal: quantify PSI, when RMPs are applied in ITER
Electron Temperature, DIII-D, with RMPs
(initially developed for stellarator applications
W7AS, W7X, LHD) was advanced to a
more flexible grid structure to allow divertor
tokamak + RMP applications. first self-consistent 3D plasma and neutral gas transport simulations for poloidal divertor tokamak configurations with RMPs.
Simulation results for ITER similar shape plasmas at DIII-D show a strong 3D spatial modulation of plasma parameter, e.g. in T
e.
EMC3-EIRENE code verification (by benchmarks with 2D tokamak edge codes) and validation (TEXTOR, DIII-D, JET, LHD experiments) ongoing
EMC3-EIRENE is currently being used for contractual ITER RMP design studies (jointly by FZJ and IPP, 2010-2012)
Te,1
= 60 eV T
e,2 = 120 eV
Te,3
= 200 eV
Towards fully 3D CFD: The EMC3-EIRENE code (IPP Greifswald – FZ-Juelich)
Atomic database, as currently used
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 40
This work: “plasma chemistry modeling
for magnetic fusion devices”
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 41
Many, external resources
www hydkin.de
B2-EIRENE
Many,
often
Matlab
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 42
www.eirene.de/A+Mdata
www.hydkin.de
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 43
www.eirene.de/A&Mdata
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 44
www.eirene.de A&M&S Data BCA: TRIM
All data, figs,
and references:
HERE
www.eirene.de: online (TRIM) reflection database
Data files with tables of
reflection distributions,
e.g. for particle simulation codes (conditional quantile format)
Backscattering
Dependency of reflection coefficient on incident energy
1 10 100 10000.00
0.05
0.10
0.15
0.20
Re
fle
cti
on
co
eff
icie
nt
R
Incident energy [eV]
Monte Carlo simulation (BCA): C on C, in = 60°
At low energies:
BCA not valid
Molecular Dynamic
calculations yield
R 0
Plasma-Wall Interaction Processes
Particle reflection coefficient, D --> FE, 30 degree
0.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
1 10 100 1000 10000
eV
Eckstein 1983
TRIM-1985
TRIM-2002
SDTrimSP 2007
Sensitivity of reflection coefficient at low Ein (all within BCA, TRIM)
Incident energy,
Uncertain
MD ??
Quite reliable,
BCA
Hidden key parameter:
Surface binding energy ( from MD?)
TRIM.xxx: reflected energy spectra
red: 200.000 TRIM particles,
blue: reconstructed from 10 quantiles
Challenge: what is the minimal dataset that allows
to re-sample the full backscattering (and sputtering) Eout,Θout-distribution ?
See:
www.eirene.de
Surface data
TRIM
E
EER inin
);,( q
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 49
TRIM-codes family, online database
for fully kinetic reflection velocity space PDFs
Particle reflection coefficient, D --> FE, 30 degree
0.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
0.8
0.9
1.0
1 10 100 1000 10000
eV
Eckstein 1983
TRIM-1985
TRIM-2002
SDTrimSP 2007
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 50
Storing full 3D pdf of reflected
particles, for given incident
energy (12) and angle (7)
i.e. 84 tables for each
target-projectile combination
Next: similar database for
sputtering.
TRIM database (www.eirene.de)
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 51
Goal: replace various scalings (e.g. Yamamura
for incident angle dependence) by full database,
same format as for EIRENE-reflection database
Still not decided:
how to parameterize
a) Surface roughness,
b) Material mixing
Universal sputtering law: Janev, Ralchenko, et al.
for normal incidence yield.
0 degree
80 degree incident angle
Sputter yield database
For normal incidence:
probably ok.
Lost information, due to
raw data processing at too early stage
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 52
www.eirene.de A&M Data HYDHEL, AMJUEL
All data, figs,
and references:
HERE
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 53
1986 -…., Polynomial fits
Automated
Interface to
EIRENE
History A&M Data, H and He, in EIRENE (=current status in ITER modelling)
1987 -…. He, He*, He+
Metastable
resolved.
Polyn. Fits
produced,
Elec. Cooling
rates added
H, H* , H+,
H2, H2+
2000 -….
Rad. transfer
Lyman opacity
added
1983 - 1999
Johnson-Hinnov
CR model for
H,H* H+
www.hydkin.de
Online data base
and data analysis tool-box:
- CR model condensation
- Sensitivity analysis
- Fragmentation pathway analysis
- Reduced models
• Hydrocarbons
• Silanes
• H, H2, H3+,….
• W, W+, ….W 74+
• N, N2
Basic input for ITER divertor code: A&M data, ( & surface data)
Goal: publicly expose raw data used in any modelling
Next GOAL: BeH, BH, ……
A: constructed from reaction rates for losses and gains of population y
(Maxw. reaction rates are obtained by integration of reaction cross sections, “on the fly”)
Gas puff, chem. sputtering Transport losses
HYDKIN: select a number of species,
and a set of reactions. Then:
NEW: surface reflection database
NEW: added after Juel-Reports and
PoP papers
Choose plasma background
Integration time
Graphical presentation
Printout:
Reflect input as selected
(composition, initial condition,
Influx, transport losses, per species)
Printout:
All individual rates used
Output for interface to EIRENE
Solution, vs. time (distance)
Here: 0 1e-4 s
Species selected for printout and plotting
Online solution of time-dep. (1D) Hydrocarbon breakup,
for any prescribed divertor plasma conditions, up to C3H8
Same, integration time 0 1e-3
Runtime of online code is independent
of chosen time interval for integration
(same for 1e-6 or 1e+6 s integration period),
time dependent solution is given fully explicitly in
terms of A matrix elements (+ initial cond.)
If A matrix is upper triagonal, all eigenvalues
and eigenvectors are explicitly given
Closed form analytic solution for Hydrocarbons: Phys. Scr. T138 (2009) 014014
Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 61
raw data
HYDKIN
database
toolbox
EIRENE
3D Monte Carlo
kinetic transport
Interface
2004 -- ……(ongoing)
TEXTOR, JET,
ASDEX, DIII-D,
JT-60, LHD, ….. ITER
Spectral (time scale) analysis
fragmentation pathways
Sensitivity analysis
Verify Interface: HYDKIN --- EIRENE
(check for correct transfer of chemisty,
correct integration of cross sections)
Periodic BC Periodic BC
EIRENE: Make one grid cell, homogeneous plasma,
source of CH4 somewhere in box, run Monte Carlo
e.g. point source of CH4 Mostly H from CH4 fragmentation
focus stat. weights on
C containing fragments
1 eV, 1000 Eirene particles (<< 1 sec cpu)
0.0E+00
1.0E+07
2.0E+07
3.0E+07
4.0E+07
5.0E+07
6.0E+07
7.0E+07
0.0E+00 1.0E-04 2.0E-04 3.0E-04 4.0E-04 5.0E-04 6.0E-04 7.0E-04 8.0E-04 9.0E-04 1.0E-03
time (s)
C Hydkin
CH Hydkin
CH_2 Hydkin
CH_3 Hydkin
CH_4 Hydkin
C Eirene
CH Eirene
CH_2 Eirene
CH_3 Eirene
CH_4 Eirene
Choose in HYDKIN and in EIRENE:
same Influx: CH4, density: 5e12 cm-3 , Te=Ti=1 eV, same [0,tmax] time period
Density of CHx vs. time
1 eV, 1000000 Eirene particles (~23 sec cpu)
0.0E+00
1.0E+07
2.0E+07
3.0E+07
4.0E+07
5.0E+07
6.0E+07
7.0E+07
0.0E+00 1.0E-04 2.0E-04 3.0E-04 4.0E-04 5.0E-04 6.0E-04 7.0E-04 8.0E-04 9.0E-04 1.0E-03
time (s)
C Hydkin
CH Hydkin
CH_2 Hydkin
CH_3 Hydkin
CH_4 Hydkin
C Eirene
CH Eirene
CH_2 Eirene
CH_3 Eirene
CH_4 Eirene
Spectral analysis:
Identification of reduced models:
ILDM
Very complex reaction chains (approx. 500 individual processes)
in fusion plasmas: catabolic sequence dominant, little: anabolism Eigenmode analysis of reaction rate equations very simple:
Define “Stiffness parameter”: λmax/ λmin,, ratio of max. to min. eigenvalues
fast slow
ILDM
Combustion and flame modelling is mathematically analog
to diffusion-reaction modelling of ITER divertor detachment.
Unfortunately: reduced models („intrinsic low dimensional manifolds, ILDM“)
only applicable at very low plasma temperatures
Full reaction
kinetics required
Spe
cie
s t
o b
e r
eta
ined
importance of CX-DR over DE-DI channels: put one CxHy into plasma. How many e,p pairs are neutralized?
p+CxHy H + CxHy+, CxHy
+ DR
DE, DI CX, DR
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 70
Molecular Data analysis (www.HYDKIN.de):
ITM , IAEA
CH4 C2H6 C3H8
DE RKJ 2009 JR 2004 JR 2004
DE+ RKJ 2009 JR 2004 JR 2004
I-DI RKJ 2009 RKJ 2009
## JR 2004 ##
DI+ RKJ 2009 JR 2004 # JR 2004 #
CX-PR JR 2002 JR 2004 JR 2004
R-DR JR 2002 RKJ 2009 RKJ 2009
JR
2002
R. K. Janev and D. Reiter, Phys. Plasmas 9,
4071 (2002);
JR
2004
R. K. Janev and D. Reiter, Phys. Plasmas 11,
780 (2004)
RKJ
2009
D. Reiter, B. Küppers, R. K. Janev, Hydrocarbon
collision database: revisions, upgrades and
extensions, Atomic and Plasma-Material
Interaction Data for Fusion, Vol 16, International
Atomic Energy Agency (IAEA), Vienna, (2010)
# new experiments planned in 2010, Univ. Louvian la Neuve, P. Defrance et al.
# # Revision planned in 2010, Univ. Innsbruck, T. Märk et al
DE: Dissociative excitation of neutral molecules
DE+: Dissociative excitation of molecular ions
I-DI: Ionisation and Dissociative Ionisation of neutral molecules
DI+: Dissociative Ionisation of molecular ions
CX-PR: Charge exchange and particle re-arrangement
R-DR: Recombination, Dissociative Recombination
2010
Upgrade disabled:
published exp. Data
inconsistent
2010
Upgrade ongoing:
Mainly: more low T
reactions:
Particle exchange
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 71
2010: more (DR) channels for Geroe Band emission added
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 72
New class of processes in thermal region
May 2011
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 73
previous database
New class of
processes (2011),
thermal region,
data from Astrophysics
Old: cx
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 74
How sensitive is a result to particular process
reaction rates (or transport losses) ?
Define sensitivity Z of density nj wrt. reaction rate Rk
as logarithmic derivative:
Z = d (ln nj) / d (ln Rk)
For n species in the system, and m different processes active,
there are n x m such sensitivity functions.
Fortunately: the system of DGL for these Z has the same form as
that for the densities n, and can also be solved in closed form
using the known eigenvalues and eigenvectors.
If this option is activated, HYKIN prints and plots the s (input)
largest (at t=tmax) such sensitivity functions
Phys. Scr. T138 (2009) 014014
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 75
HYDKIN.de: online sensitivity analysis
Analytic solution for sensitivity,
online
Zjk(t)=d(ln[nj])/d(ln<ratek>)
Identify, print and plot the most
sensitive parameters:
If <ratek> changes by x %
Then nj changes by x * Zjk %
Breakup of CH4 @ 40 eV
(143 parameters)
At 40 eV (TEXTOR)
Only DE, I, DI processes are relevant,
(nearly) no dependence on transport at all
D.Reiter et al., Phys. Scr. T138 (2009) 014014
Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 76
HYDKIN.de: online sensitivity analysis D.Reiter et al., Phys. Scr. T138 (2009) 014014
Identify, print and plot the most
sensitive parameters:
If <ratek> changes by x %
Then nj changes by x * Zjk %
Breakup of CH4 @ 2 eV
(143 parameters)
At 2 eV (detached divertor, PSI-2)
Only CX, DR processes are relevant,
strong dependence on transport details
Analytic solution for sensitivity,
online
Zjk(t)=d(ln[nj])/d(ln<ratek>)
Conclusions/Outlook
Similar to previous steps: progress to ITER is based mainly on experimental and empirical extrapolation
guided by theory and aided by modelling
Present goal:
include all of edge physics that we are sure must be operative (opacity, A&M physics, surface processes, drifts…, even while our capability to confirm these directly remains limited.
Codes = bookkeeping tools
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)