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The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application)...

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Member of the Helmholtz Association Detlev Reiter | Institute of Energy Research Plasma Physics | IAEA meeting on “Technical Aspects of Atomic and Molecular Data Processing and Exchange (21th Meeting of the A+M Data Centers)”, 7-9 September 2011, IAEA Headquarters, Vienna, Austria The EIRENE.DE online database for surface and A+M data in fusion edge modelling
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Page 1: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

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Detlev Reiter | Institute of Energy Research – Plasma Physics |

IAEA meeting on “Technical Aspects of Atomic and Molecular Data Processing and Exchange

(21th Meeting of the A+M Data Centers)”, 7-9 September 2011, IAEA Headquarters, Vienna, Austria

The EIRENE.DE online database for

surface and A+M data in fusion edge modelling

Page 2: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 2

OUTLINE

I Motivation (very short)

II Current plasma chemistry modeling activities in FZJ (short)

III Hydrogen and Helium Chemistry in Fusion Plasmas:

the EIRENE code and the HYDKIN online toolboxes

Page 3: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

div(nv║)+div(nv

┴)= ionization/recombination/charge exchange

II: midplain

III: target

Relative importance of plasma flow forces over chemistry and PWI

I core plasma II edge region III divertor

parallel vs.

(turbulent)

cross field

flow

parallel vs.

chemistry

and PWI

driven flow

div(nv║)+div(nv

┴)= ionization/recombination/charge exchange

Dominant friction: p + H2

Page 4: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 4

EMC3 (& B2)

CFD, 2D & 3D

Charged fluid parcels

m – 100 m scale

EIRENE

3D kinetic

Gyro centers,

Entire SOL and Core

mm - m scale

ERO, PEPC

“Real” ions (and electrons)

PSI in plasma, near solid

(sub-) cm scale

ITER

Integrated edge plasma simulation:

“From the barrier to the target” Drift-Fluid turbulence:

Attempt

PMI inside solid: TRIM.xxx,

Material science etc…,

nm-scale

MICRO

MACRO

Input:

Transp. Coeff.

Input:

Kinetic boundary

conditions

Mostly ITER

contractual work

Page 5: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 5

ITER, B2-EIRENE simulation, fully detached, Te field

hotter than

1 Mill deg.

Page 6: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 6

B2 – EIRENE (ITER, since 1991, TEXTOR, ASDEX,…many more ) (FV, 2D)

OSM – EIRENE (D-IIID, ITER,….)

EDGE2D – EIRENE (JET, since 2007) (FD, 2D)

EMC3 – EIRENE (W7AS (1999) , TEXTOR, W7X,…ITER (2010) (MC, 3D)

FIDAP – EIRENE (Philips Lighting, finished, lamps marketed in 2008) (FEM, 3D)

+….many stand alone applications to specific physics questions

Atomic, Molecular and Surface physics is mainly integrated into fusion edge

plasma codes via kinetic (Monte Carlo) solvers:

DEGAS-2 (US), NIMBUS (stopped), NEUT2D (JP), EIRENE (EU) , …

Page 7: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 7

Numerical tool for the edge plasma transport: B2-EIRENE code package

B2: a 2D multi species (D+, He+,++, C4+..6+,…) plasma fluid code

EIRENE: a Monte-Carlo neutral particle, trace ion (He+, C+, C++) and radiation transport code.

Plasma flow Parameters

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

CR codes: HYDKIN

SOLPS4.3: ITER.org (Cadarache) – FZ Juelich jointly developed and applied: since about 15 years

Page 8: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 8

ITER contractual edge modelling

Goal: quantify PWI, when RMPs are applied in ITER (EMC3-EIRENE 3D tokamak edge transport application)

F4E-GRT-055 (PMS-PE) ,

FZJ-IPP-CEA

(since july 2010)

ITER.CT.09.4300000034

FZJ (since Oct. 2009)

Goal: diagnostic mirror lifetime assessment (closing the gap between SOL and wall in B2-EIRENE)

SOLPS4.x (ITER, FZJ) vs. SOLPS 5.y (IPP) F4E-OPE-258 FZJ, Univ. St. Petersburg, (Dec. 2010)

CXRS port plug,

CATIA design

1st mirror

EIRENE code model

via ANSIS interface

(mirror lifetime assessment) Be erosion rate in

CXRS port plug

Page 9: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 9

Aperture

First mirror

2nd

mirror

I) CAD design

II) grid generation

ANSYS

III) 3D EIRENE

Monte Carlo Simulation

Erosion, Deposition

(lifetime) of mirrors

FZJ activities:

Plasma Chemistry Modeling for Fusion

Color: erosion rate

inside port plug by

Be wall impurities

First mirror

First mirror

BES,

CXRS,

Data:

O.Marchuk et al.

PMI data: TRIM.xxx

Page 10: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

After 12 years “computational engineering” for ITER divertor

2007: ITER design review: ALARM….

Kukushkin A., Kotov. V., Reiter D. et al., Nucl. Sci. Eng., 2011, to appear

The ITER design review found that PF

coil set would not support range of

operating space for 15 MA, QDT = 10

inductive scenario goals to be met

when more realistic assumptions used

excessive V-s consumption during Ip ramp-up restrictions on flattop time

peaked current profiles during ramp-up instability

broader current profiles due to H-mode pedestal PF6 coil current and field limits exceeded

central solenoid separation forces restricting operational space

divertor dome and slot clearances of 2007 design too small for nominal operating points and during disturbance transients

Modification of PF system Change in equilibrium

Page 11: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 11

2004 reference 2009 reference

F46 F57

Calculations slow so use the previously studied variants to see the progression

Extend parallelization of EIRENE to B2-EIRENE (2008), + HPC-FF, ….

li=0.8

0.8

0.8 0.63

0.7

0.7

The geneology of ITER divertors

2007-2009: New reference design B2-EIRENE: main ITER edge plasma design tool

Kukushkin A., Lisgo, S. et al. (ITER IO)

Kotov. V., Reiter D. et al., (FZ-J)

Pacher G. et al. (INRS-EMT, Varennes, Québec, Canada)

Page 12: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 12

This work: “plasma chemistry modeling

for magnetic fusion devices”

Page 13: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 13

Many, external ressources

www hydkin.de

B2-EIRENE

Many,

often

Matlab

Page 14: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 14

www.eirene.de/A+Mdata

www.hydkin.de

Page 15: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 15

www.eirene.de/A&Mdata

Page 16: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy and Climate Research – Plasma Physics | Association EURATOM – FZJ No 16

www.eirene.de A&M Data HYDHEL, AMJUEL

All data, figs,

and references:

HERE

Page 17: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 17

Our own homemade “database” for fusion

plasma chemistry modelling,

in this sense described by M. Kushner,

is publicly exposed on: www.eirene.de

Methane (CHy) C2Hy C3Hy Silane (SiHy)

Reviewed EIRENE database Series 2002-…., (several IAEA CRP’s)

FZ-Jülich (R. Janev, D. Reiter et al.) www.eirene.de www.hydkin.de

p,H,H-,H2,H2+,H3

+

JUEL 4005, Oct. 2002

Phys. Plasmas,

Vol 11,2, (2004) 780

JUEL 3966, Feb 2002

Phys. Plasmas,

Vol 9, 9, (2002) 4071

JUEL 4038, Mar. 2003

Contr. Plas.Phys,

47, 7, (2003) 401-417

JUEL 4105, Dec. 2003

Encycl. Low. Temp.

Pl. 2007 (in russian)

Page 18: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 18

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 EIRENE: A&M data, ( & surface data)

Goal: publicly expose raw data used in any modelling

Next GOAL: BeH, BH, ……

Page 19: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 19

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

Page 20: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 20

Molecular Data analysis (www.HYDKIN.de):

IAEA, Data centers (ORNL, NIFS, …)

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, R. K. Janev, Hydrocarbon collision

database: revisions, upgrades and extensions,

Atomic and Plasma-Material Interaction Data for

Fusion, Vol 16, IAEA, Vienna, (2011) , and:

Contr. Plasma Phys. (2010)

# new experiments planned Univ. Louvian la Neuve, P. Defrance et al.

# # Revision planned in 2011, Univ. Innsbruck, S. Huber et al., CPP 2011, in printing

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

2011

Upgrade ongoing:

more low T reactions:

Particle exchange

Example: Hydrocarbon cross section database

Page 21: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 21

www.hydkin.de

Major difference to other online A@M toolboxes:

Not COLL. RAD., but SPECTRAL A@M modelling

(needed in transport codes for time-scale analysis)

Online sensitivity analysis possible !

Perhaps in the future:

Revised data reduction scheme (ILDM rather than CR):

Dauwe,Tytgadt, Reiter, JUEL 4229, Nov. 2006,

Availabe on www.eirene.de/html/relevant_reports

Page 22: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 22

HYDKIN.de: online sensitivity analysis

Analytic solution for sensitivity,

online

Z(t)=d(ln[nY])/d(ln<rate>)

Identify, print and plot the most

sensitive parameters:

If <rate> changes by x %

Then nY changes by x * Z %

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

Phys. Scr. T138 (2009) 014014

Page 23: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 23

HYDKIN.de: online sensitivity analysis Phys. Scr. T138 (2009) 014014

Analytic solution for sensitivity,

online

Z(t)=d(ln[nY])/d(ln<rate>)

Identify, print and plot the most

sensitive parameters:

If <rate> changes by x %

Then nY changes by x * Z %

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

Page 24: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 24

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

Page 25: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 25

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)

Page 26: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 26

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

Page 27: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 27

Backup slides

Page 28: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Generic kinetic (transport) equation (L. Boltzmann, ~1870)

,,,,

EfEvESForcesEfvt

Efa

40

,,,,

EfEEvEfEEvdEd ss

• for particles travelling in a background (plasma) between collisions

• with (ions) or without (neutrals, photons) forces

(Lorentz, or guiding center) acting on them between collisions

),,( tvrf

Basic dependent quantity: distribution function

Free flight External source Absorption

Collisions, boundary conditions

Altogether, just a balance in phase space

The kinetic equation solved by EIRENE: www.EIRENE.de

Page 29: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

CR Models in Transport Codes

1) System of N kinetic (or fluid) equations

(PDE, IDE), one for each species: H, H*, Lyα…

2) select M species, remove transport term

and explicit time derivative

(Interpretation: their lifetime is short compared to transport

time)

3) System reduced to N – M transport equations

plus one linear algebraic system (CR Model), of

order M

The M states are in quasi steady state with

the N – M transported species.

CR models are QSS models

Page 30: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Kinetic (transport) equation IDE, one for each species

ForcesEfvt

Ef

,,

40

,,,,

EfEEvEfEEvdEd ss

Transport External source Absorption

Collisions, Boundary Conditions

,, EfEvES a

f

t

Ef

,

System of reduced eqs. then becomes analogous to ODE:

SfMf

tfor those fi, for which the transport has been

removed from kinetic equation

EIRENE:

NFOLi=-1 option 0

0 =

Provides fully user controlled condensation of plasma chemistry

into CR model,

retaining all parametric dependencies

in multidimensional reduced rates

but, of course is also a patently foolisch way to build CR models

(by “Monte Carlo matrix inversion”).

for user selected states/species

(problem specific)

Page 31: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

N species: Result: coupled system:

• No general rules for “condensation” of chemistry matrix M exist.

• Optimal condensation is highly cases dependent.

• Transport codes do not need CR-Model data (eff. rate coeffs.),

but the Master Matrix M and a solver “on the fly” embedded

as sub-module into them.

• No a-priory “bundling” of states.

SfMf

t

+ M algebraic eqs.

N-M coupled Boltzmann eqs. for: fi, i=1,…N-M

for: fi, i=N-M+1,…M

Page 32: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 32

NEW

Page 33: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 33

Revisions 04-09:

APID Vol. 16 (2011)

Issue: backward compatibility

Page 34: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 34

NEW: surface reflection database

NEW: added after Juel-Reports and

PoP papers

Page 35: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 35

Choose plasma background

Integration time

Graphical presentation

Page 36: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 36

Printout:

Reflect input as selected

(composition, initial condition,

Influx, transport losses, per species)

Printout:

All individual rates used

Output for interface to EIRENE

Page 37: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 37

Solution, vs. time (distance)

Here: 0 1e-4 s

Species selected for printout and plotting

Page 38: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 38

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)

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Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 39

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Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 40

Spectral analysis:

Identification of reduced models:

ILDM

Page 41: The EIRENE.DE online database for surface and …(EMC3-EIRENE 3D tokamak edge transport application) F4E-GRT-055 (PMS-PE), FZJ-IPP-CEA (since july 2010) ITER.CT.09.4300000034 FZJ (since

Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 41

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

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Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 42

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

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Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 43

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Detlev Reiter | Institute of Energy Research – Plasma Physics | Association EURATOM – FZJ No 44


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