1 / 23

Transport simulation of current ramp-up & ramp-down by F. Imbeaux* presented by X. Litaudon*

Transport simulation of current ramp-up & ramp-down by F. Imbeaux* presented by X. Litaudon*. Association Euratom- cea. *.

spike
Télécharger la présentation

Transport simulation of current ramp-up & ramp-down by F. Imbeaux* presented by X. Litaudon*

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Transport simulation of current ramp-up & ramp-down by F. Imbeaux* presented by X. Litaudon* AssociationEuratom-cea * F. Imbeaux, F. Köchl, V. Basiuk, J. Fereira, J. Hobirk, D. Hogeweij, X. Litaudon, J. Lönnroth, V. Parail, G. Pereverzev, Y. Peysson, G. Saibene, M. Schneider, G. Sips, G. Tardini, I. Voitsekhovitch On behalf of : JET-EFDA contributors, Tore Supra work programme, ITER Scenario Modelling group (ITM-TF)

  2. Modelling of current ramp • Aim of the working group: model current ramp-up (and down) in ITER • Implications on PF system design, • H&CD methods for current profile shaping • flux consumption • Main issues are related to the transport model  try to validate a model against present experiments • Validation: li , Vloop, Te, Ti test against several JET, Tore Supra AUG, experiments (ohmic, NBI, LHCD, ECCD) • Up to now, energy and current diffusion are modelled • L mode edge plasmas 2

  3. Consideration on current ramp transport modelling • Choice of the transport model : scaling-based, empirical, 1st principles • Li prediction and Flux consumption strongly depend on the Te at r >0.5 • Model has to predict Te up to r = 1 with L-mode edge • Scaling-based transport model are • a priori less sensitive to the assumptions on the boundary conditions (stiffness issue, drift wave models not accurate close to the edge) • Have hopefully a correct dependence on Ip and machine size for extrapolation • May miss several physical effects  try to validate on extensive range of machines / heating schemes • empirical models: Bohm/gyro-Bohm and Coppi-Tang have been tried as well • Validation on existing experiments is essential • Excellent opportunity for code-to-code benchmarking : • Jetto and Cronos used in comparison with experimental data • Astra, Jetto, Cronos used in ITER predictions 3

  4. Database from JET, Tore Supra, AUG with various H&CD mix TORE SUPRA • Current ramp-up for base-line (q95~3) & AT scenario (q95~5) : AUG 22110 (ohmic) just added last week } To be transferredto ITPA database • Current ramp-down from base-line scenario (2.4T/2.7MA, q95~3): • Pulse ramp-down additional heating • JET 72200 slow none • JET 72202 fast none • JET 72210 fast NBI heating until ramp-down • JET 72241 fast NBI heating after ramp down (in low Ip phase) 4

  5. Scaling-based model • Scaling-based model: energy content of ohmic or heated Ip ramps with L-mode edge correctly modelled by either • H mode scaling with H98 = 0.4 – 0.5 • L mode scaling with H97 = 0.6 • ci = ce, renormalised so that • Fixed c(r) shape : power balance chi’s during ramp-up tend to be rather flat, then strong increase towards the plasma edge : c(r,t) = A(t)(1+6 r2 + 80 r20) • Boundary Te (r = 1) taken from experiment (guessed from ECE) • Ne profile taken from experiment (JET: inversion of interferometry data) • Flat Zeff assumed, <Zeff> taken from experiment (Bremsstrahlung) 5

  6. Calibration on JET shot 70497 (constant q95 ~3 ohmic ramp-up) • Model ci = ce, renormalised to IPB98 scaling, H98 = 0.5 (mimics L mode), radial shape 1+6 r2 + 80 r20 (adjusted to fit experimental Te profile peaking). • Te is correctly reproduced. • CRONOS simulation red - : Simulation blue * : ECE Purple * : Thomson scattering 2.6T/2.6MA, q95~3 t = 0.5 s t = 2 s t = 4 s t = 5 s 6

  7. Apply same model on another ohmic ramp for AT scenario (JET #72818) • Model ci = ce, renormalised to IPB98 scaling, H98 = 0.5 (mimics L mode), radial shape 1+6 r2 + 80 r20 (adjusted to fit experimental Te profile peaking). • Te is well reproduced for r > 0.6. Even if larger deviations occur inside r = 0.6, they almost do not affect the li evolution. • Li slightly overestimated, Dli ~ 0.08, ~ measurement accuracy. • Vloop good, slightly underestimated 2.7T/1.8MA, q95~5 t = 6 s Simulation ECE Thomson scattering time (s) time (s) 3 4 5 6 3.5 4 4.5 5 5.5 7 ITPA meeting Milan, October 2008, F. Imbeaux

  8. Ohmic Ip Ramp-down (JET 72202) 2.4T/2.7MA down to 1.0MA JETTO Experimental Bohm/gyro-Bohm* Scaling, H98 = 0.5 • Both models follow equally well li and the volume averaged Te time (s) *without non-local Bohm multiplier 14 16 18 20 22 24 8

  9. Ohmic Ip Ramp-down (JET 72202) r • Comparison of the two models : some difference in Te profile peaking, that Bohm/gyro-Bohm provides a better agreement (for JET) • A possible approach consists in combining: profile dependence as B/gB + scaling renormalisation for multi-machine capability ? JETTO Experimental Bohm/gyro-Bohm Scaling, H98 = 0.5 9 r

  10. LHCD assisted ramp-up in AT scenario(JET 72823) • Scaling base model, H98 = 0.4 • LHCD calculated during interpretative run • Li slightly overestimated, Dli ~ 0.1 2.7T/1.8MA, q95~5 3 4 5 6 2 time (s) time (s) 5 6 3 4 3 4 5 6

  11. LHCD assisted ramp-up for AT scenario(JET 72823) Excellent fit of the volume averaged temperatures, both electron and ion Simulation ECE Thomson Scattering 2.7T/1.8MA, q95~5 t = 3 s t = 4 s t = 5.5 s

  12. LHCD assisted ramp-up for AT scenario(JET 72823) • NBI blips (MSE & CXS) during current rise : • CXS & MSE measurements 2.7T/1.8MA, q95~5 Ion temperatures from CXS TI TI t = 4 s t = 5 s Simulation *CXS

  13. LHCD assisted ramp-up for AT scenario(JET 72823) • NBI blips (MSE & CXS) during current rise : • CXS & MSE measurements 2.7T/1.8MA, q95~5 t = 4.5 s t = 5.5 s • Comparison to MSE q-profile (EFTM)

  14. First attempts to test GLF23 in JET ramp-up phase Te Ti • When applied from the edge at high q (JET 71828, ohmic, 1 s after breakdown, 5 < q < 15) • Very low transport predicted near the edge (r = 1)  barrier forms and non monotonic Te profiles appear (2.6T/2.6MA, q95~3 at flat top ) JET 77251 5.5s JET 71828 t=1s After breakdown Exp Normalised radius • When trying to patch the edge (impose c = 10 m2/s from r = 1 to r = 0.75), the same problem appears at r = 0.75 • Possibility to use GLF23 ? : on the whole radius ? At high q ?

  15. Tore Supra ramp-up experiments TORE SUPRA • Fast current ramp (0.7 MA/s), plateau Ip = 0.9 MA reached at t = 1 s • off-axis co-ECCD (.7 MW) and/or LHCD (.8 MW) during ramp at t = 0.25s • Same li evolution, but different Te evolution & time of first sawtooth Blue : usual scaling-based model H98 = 0.5 Green / red: two experimental measurements of li TS40676 : ECCD TS40679 : LH+ECCD

  16. 1st set of simulation: ITER ramp with constant boundary shape • L-mode transport model: (r) validated on JET & TS with H98 = 0.5. • The edge temperature set to Tb=20*Ip[MA] eV, although with the chosen transport model Tb assumption is not that important. • Use a formula for Zeff (used by the ITER team): • Zeff = (1.7+2.3x(0.5/ne)2.6)), Carbon is main impurity • The current ramp follows the ITER reference one with 15MA at 100s: • 1.5MA t=4s, 3.0MA t=8s, 7.5MA t=30s, 13MA t=75s, and 15MA t=100s. • The simulations start at 3MA (t=8s), with an initial condition for the q-profile (li=1) and a temperature profile. • ITER divertor shape from Ip3MA: full bore plasma. • densities <ne>/nGW = 0.15; 0.25; 0.4 (low to medium density). • Use a variation of heating: Ohmic, 10MW and 20MW of ECRH with power deposition at mid-radius (heating only, no current drive). 16 ISM Working group

  17. Modelling of ITER ramp with various heating & densities <ne>/nGW = 0.25 <ne>/nGW = 0.4 <ne>/nGW = 0.15 10 MW ECRH <ne>/nGW = 0.25 20 MW ECRH <ne>/nGW = 0.25 17 Working group D. Hogeweij et al, EPS 2008

  18. Modelling of ITER ramp with various heating at <ne>/nGW = 0.15 D. Hogeweij et al, EPS 2008 Te profile evolution. Hollow profiles achieved transiently with off-axis ECRH, still present at the end of the ramp Te ITB may be obtained with such hollow q-profiles (not in the model) 18 Working group

  19. 2nd set of simulation: ITER ramp with evolving boundary shape ASTRA CRONOS JETTO JET like Tore Supra like 19 ISM Working group

  20. 2nd series: ITER with prescribed evolving boundary shape • Ohmic ITER ramp-up, time-dependent plasma boundary (preset), using the same model as before, H98 = 0.5 • Code comparison: rather close agreement between CRONOS and JETTO, in spite of the differences in the treatment of equilibrium, transport coefficient renormalisation, … • Detailed code comparison starting from basic simulations going on between ASTRA and JETTO 20 Working group

  21. Perspectives • Up to now, mainly the scaling-based model was used, work being extended to empirical models like Bohm/gyro-Bohm and Coppi-Tang • Test on multiple machine data : JET, Tore Supra and Asdex Upgrade • Rather good agreement with experimental data (on Te, li and Vloop prediction) has been found in several cases. None of these models can be ruled out yet. • Analysis still in progress, more detailed trends / observations to be given when the full database analysis will be completed • Multiple transport codes working on the same dataset allow detecting bugs / sensitivity to unexpected parameters / assumptions • Coppi-Tang implementation : still doubts on a few details (definitions of some quantities)  need to have the same as in TSC • Extend data base to other heating schemes, other machines (ITPA) should contribute to further validate the models • Continue testing other models : • introduce more sophisticated radial dependence in scaling-based ? Try further GLF23, through first attempt was quite unsuccessful • Include free-boundary equilibrium calculations : try for the end of 2009

  22. JET ohmic ramp-up 71828 • Electron energy content well fitted by H98 = 0.4 or H97 = 0.6 • Also by “old Bohm/gyro-Bohm model”, i.e. without the edge “H-mode” factor. However, can we expect that it would work so well on other tokamaks ? • Coppi-Tang model not accurate Black dots : experimental data from LIDAR (Thomson scattering) G. Sips et al, EPS 2008

  23. First attempts to test GLF23 in JET ramp-up phase Te Ti • When applied from the edge at high q (JET 71828, ohmic, 1 s after breakdown, 5 < q < 15) • Very low transport predicted near the edge (r = 1)  barrier forms and non monotonic Te profiles appear (2.6T/2.6MA, q95~3 at flat top ) Normalised radius • When trying to patch the edge (impose c = 10 m2/s from r = 1 to r = 0.75), the same problem appears at r = 0.75 • Possibility to use GLF23 ? : on the whole radius ? At high q ?

More Related