1 / 12

T&C ITPA group meeting, 4-6 April 2011

wmbass
Download Presentation

T&C ITPA group meeting, 4-6 April 2011

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. Draft of ISM talk on T&C ITPA for discussion/completion: ISM modelling activity on current ramp upPresented by I VOITSEKHOVITCH on behalf of ISM groupTF Leader : G. Falchetto Deputies: R. Coelho, D. CosterISM Leader: X. LitaudonISM Deputy Leader: I. Voitsekhovitch EFDA CSU Contact Person: D. Kalupin T&C ITPA group meeting, 4-6 April 2011

  2. Outline • Introduction • Validation of transport models for current ramp up plasmas • Current diffusion: is it consistent with neoclassical predictions? • Projection to ITER

  3. About ISM: general information • Created in 2007 as ITM cross-project. Status of ITM project since 2010 • Activity proceeds via: 3 working sessions per year + regular remote meetings (~every two weeks). • Resources in 2010/2011: - 47 participants, 6.86 PPY (Basic and priority support) - CCFE, CEA, ENEA, IPP-Garching, IST-Portugal, FOM, FZJ, RFX, OAW, VR, EFDA-CSU - coordinated by X. Litaudon (Leader) and I. Voitsekhovitch (Deputy) • Suites of codes involved: ASTRA, CRONOS, JETTO, TRANSP, SANCO, SOUL 1D, EDGE2D, EMC3-EIRENE, MISHKA, METIS, HELIOS. ETS (European Tokamak Solver) at the user test phase. • Close collaboration with IO, ITPA groups (T&C and IOS) and experimentalists (JET, AUG, Tore Supra)

  4. Scientific activities: • Activity-1 : Support Validation of the ETS • Activity-2 : Developing and validating plasma scenarios: simulations for existing devices • Activity-3 : Support to predictive scenario modelling for future devices (ITER , JT60SA, etc)

  5. Validation of transport models • Multi-machine database for modelling: AUG, JET, Tore Supra. DIII-D in collaboration with T&C ITPA group. Operational space: dIpl/dt=0.19-0.36 (JET)-0.7 (AUG)-0.8(TS) MA/s, n/nGW=0.2-0.4, q95=3-5(TS), Paux= 0.7(TS) -10 MW: ICRH, NBI, LHCD, ECCD • Tested models: scaling-based model with prescribed radial shape of e = i, semi-empirical models: Bohm-gyroBohm and Coppi-Tang; GLF23 G.M.D. Hogeweij et al, EPS 2010 5 s Te keV 11 s 0.6MW of ECCD (at =0.3) applied from 0.5 till 3.5 s. Profiles at 1 s (halfway the Ip ramp up) OH Ip ramp up phase of JET pulse 71827 Other slices? Difs btw central TS&ECE?

  6. Benchmarking of Coppi-Tang model in ASTRA & CORSICA for DIII-D OH current ramp up discharge with diagnostic beam blips Tom Casper, Irina Voitsekhovitch, ISM WS Nov 29- Dec. 3 2010, Culham ASTRA CORSICA 1.4 s 0.7 s Sqrt(tor flux) • implementation: CORSICA = 2.5ASTRA = 2.5*CT as defined in [Jardin et al NF 1993]. The multiplier 2.5 is used for OH and L-mode only • input data: different ne(r) – more peaked profiles in CORSICA • results: better agreement than previously, but Te is still different. Different POH(r)

  7. Validation of transport models - summary • Summary for transport models - empirical scaling-based: the optimal agreement between experiment and simulations is obtained using either H96-L = 0.6 or HIPB98 = 0.4. - Bohm-gyroBohm: good predictive capability for JET discharges with central heating, over-predicts Te in discharges off-axis heating. OH discharges: predictive accuracy varies depending on q evolution - GLF23: accurate predictive capability in NBI heated plasmas at low power, but less accurate at high power • Coppi-Tang model: - 8Coppi-Tang for OH plasmas, (4.7-4.9)Coppi-Tang for NBI and ICRH heated discharges [I. Voitsekhovitch et al, PPCF 2010] – better agreement with these results when the factor 2.5 has been taken into account, but still a larger multiplier is needed to match the JET discharges

  8. Current diffusion I. Jenkins et al EPS 2010 • I. Jenkins et al [EPS 2010]: early MSE measurements (@~1s) after the breakdown at JET AT scenario: too fast reduction of q0 • G.M.D. Hogeweij et al [], I. Voitsekhovitch et al [PPCF 2010] – too rapid reduction of q0 in JET ITER-like discharges with flat Zeff (Zeff2), but possible to match q0 by playing with Zeff profile and using NCLASS • I. Voitsekhovitch et al, coming IOS ITPA: accurate NCLASS prediction of q profile evolution for 3 DIII-D discharges (Zef  1.5) Zef: 5-3 I. Voitsekhovitch, ISM meeting 10.11.2010 Rgeo from ONETWO, matched plasma volume, data JET 72823 (LH), 5s

  9. li simulations • li simulations with different transport models [F. Imbeaux et al, ITPA 2010] • Sensitivity study by Joerg: li is highly sensitive to edge q, while even significant changes in the central part of q-profile are not necessarily visible in li li(3)=1.11 (solid), 1.26 (dashed) li(3)=1.248 (solid), 1.263 (dashed) ? JET ohmic shot 71827: the plasma current is ramped up to 2.5 MA in 10 s. Te profils are shown at 5 s

  10. Projections to ITER: sensitivity to transport models G.M.D. Hogeweij et al, EPS 2010 I. Voitsekhovitch et al, PPCF 2010: ECRH heated current ramp up GLF23, BgB time=80 s GLF23, BgB Te0 Ti0 OH ramp-up phase with ne/nGW=0.25: profiles of Te, at 100 s (endof the Ip ramp-up), as calculated by 2 transport models, under different assumptions regarding Te(edge) and ne profile shape. time=80 s Scan in ECRH power and power deposition at ne/nGW=0.5

  11. ISM work in progress: • Modelling of current ramp up for JET HS • Optimisation of current ramp up for ITER HS (G.M.D. Hogeweij et al, EPS 2011) • Current ramp up simulations for DIII-D and comparison with JET [I. Voitsekhovitch et al, IOS ITPA group meeting, April 11-14 2011 Place for nice figure with recent results

  12. Publications used in this talk: • Hogeweij G.M.D., et al, Controlled Fusion and Plasma Physics (Proc. 34th Eur. Conf.,Dublin, Ireland, 2007) • V. Parail et al Integrated modelling o ITER reference scenarios, Nucl. Fusion 49 (2009) 075030 3. Hogeweij G.M.D., Citrin J., Garcia J., et al, Current ramp-up in tokamaks from present experiments to ITER scenarios, Controlled Fusion and Plasma Physics (Proc. 37th Eur. Conf.,Dublin, Ireland, 2010), CD-ROM file P1.1041 4. Imbeaux F, Basiuk V, Budny R, et al, Current ramp-ups in tokamaks: from present experiments to ITER scenarios, 23rd IAEA Fusion Energy Conference (ITR/P1-20), Daejon, Republic of Korea, October 10-16th 2010, to be submitted to Nuclear Fusion 5. I. Voitsekhovitch et al, PPCF 2010 6. I. Jenkins et al EPS 2010

More Related