34 th European Physical Society Conference on Plasma Physics, Warsaw , July 2-6, 2007

1. 34th European Physical Society Conference on Plasma Physics, Warsaw, July 2-6, 2007 • LOC: INSTITUTE of PLASMA PHYSICS and LASER MICROFUSION Association EURATOM-IPPLM • Conference site: The Palace of Culture and Science,Warsaw • 4 topics in parallel : Magnetic confinement fusion MCF; Beam plasma and inertial fusion (BPIF); Dusty and low temperature plasma (DLTP); Basic plasma and space and astrophysical plasma (BPS/A) • One main hall and 3 parallel halls for oral presentation • Satellite meetings: "Dust in Fusion Plasmas", and "10th Workshop on Electric Fields, Structures, and Relaxation in Edge Plasmas" • Accommodation: 15min. by walking

2. 34th European Physical Society Conference on Plasma Physics, Warsaw, July 2-6, 2007 • Magnetic confinement fusion MCF, 436 • Beam plasma and inertial fusion (BPIF), 81 • Basic plasma and space and astrophysical plasma (BPS/A), 48 • Dusty and low temperature plasma (DLTP), 52 • P/I/O---- P(11), I/O (135) • MCF: P(4), I/O (47) • BPIF: P(4), I/O (39) • DP/LTP: P(1), I/O (19) • BPS/A: P(2), I/O (30)

3. Parallel invited talks on34th EPS Conference on Plasma Physics • H. Bindslev (Risoe, Denmark): Fast-Ion Dynamics in the TEXTOR Tokamak Measured by Collective Thomson Scattering. • I. Chapman (Culham, UK): The Physics of Sawtooth Stabilization. • E. Kruglyakov (Novosibirsk): Recent Progress in Plasma Confinement and Heating in Open– Ended Magnetic Traps. • U. Fantz (IPP Garching, Gemany): Development of a Negative Ion RF Source for ITER NBI. • R. Neu (IPP Garching, Germany): Plasma wall interaction and its implication in an all tungsten divertor tokamak. • H. Zohm (IPP Garching, Germany): Control of MHD Instabilities by ECCD on ASDEX Upgrade in view of ITER Application. • L. Colas (CEA Cadarache, France), Understanding the 2D spatial structure of RF-induced SOL modifications. • V. Grandgirard (CEA Cadarache, France): Global full-f gyrokinetic simulations of plasma turbulence. • T. Rhodes (LA, USA): Response of Multi-Scale Turbulence and Plasma Transport to Electron Cyclotron Heating in the DIII-D Tokamak. • H. Yamada (NIFS): Japan Characterization and Operational Regime of High Density Plasmas with Internal Diffusion Barrier Observed in Large Helical Device.

4. Parallel invited talks on34th EPS Conference on Plasma Physics • Zhihong Lin (California, USA): Nonlinear dynamics of ETG and CTEM turbulence and their interaction with zonal flows. • Y. Liang (FZJ Jülich, Germany): Active control of type-I edge localized modes on JET. • P. Andrew (Culham, UK): Transient heat loads on the JET main chamber wall. • B.P. Duval (CRPP Lausanne, Switzerland): Bulk plasma rotation in the TCV Tokamak in the absence of external momentum input. • O. E. Garcia (Risoe, Denmark): Convective transport by filamentary structures in scrape-off layer plasmas. • X. Litaudon (CEA, France): Development of steady-state scenarios compatible with ITER wall conditions. • L Marrelli (Padova, Italy): Combined RFX talk: Magnetic self-organization, MHD active control and confinement in RFX-mod, High current and density regimes in RFX: improved confinement and high density limit. • H. Reimerdes (Columbia, USA): Resistive Wall Mode Stabilization in Slowly Rotating High Beta Plasmas.. • N. Gorelenkov (PPPL USA): Predictions and Observations of Global Beta-induced Alfven-Acoustic Modes

5. 34th European Physical Society Conference on Plasma Physics, Warsaw, July 2-6, 2007 Magnetic confinement fusion MCF…ITER • H-mode (mechanism…..) • Turbulence and confinement (ETG, CTEM,…pellet,… T/S/E) • MHD (NTM, RWM, rotation by momentum injection, ripple…..) • ELMy (filament, control, pellet, divertor….) • Diagnotics (CXRS, T.M. Biewer; fast ion, TJ-II; IR camera…..) • PSI: SOL (ASDEX W source, LHCD+ICRF in W, retention, erosion, radiation damage…. ), • Theory, simulation and experiment • Dust

6. Error field correction coils on JET • EFCCs are four square shaped coils (~ 6m x 6m) positioned outside of JET vessel • ICoil ≤ 3 kA x 16 turns • Original purpose of these coils is to compensate n=1 intrinsic error field • Depending on the relative phasing of the currents in individual coils, either n=1 or n=2 fields can be generated Y. Liang, 34th EPS, Warsaw

7. #67959 17.79 17.78 17.80 Time (s) Reduction in ELM energy loss DW/W without n = 1 field with n = 1 field Da #67954 Da WDia WDia 16.66 16.60 16.72 Time (s) DW/W : ~ 7% ↓ below 2%Y. Y. Liang, 34th EPS, Warsaw

8. Toroidal field ripple effects on H-modes in JET and implications for ITER G Saibene (1), R Sartori(1) , P de Vries (2) , A Loarte (1) , J Lönnroth (3) , V Parail (2) , A Salmi (3) , PR Thomas (4) , P Andrew (2) , Y Andrew (2) , R Budny (5), A Boboc (2) , I Coffey (2) , E de la Luna (6) , PJ Lomas (2) , S Gerasimov (2) , C Giroud (2) , J Hobirk (7) , S Hotchin (2) , T Johnson (8) , C Lescure (2) , DC McDonald (2) , I Nunes (9) , N Oyama (10) , V Riccardo (2) , H Urano (10) , and JET EFDA contributors(*) (1) EFDA CSU-Garching, Germany, (2) Euratom/UKAEA Assoc., Culham Science Centre, UK, (3) Assoc. EURATOM-Tekes, Helsinki Univ. of Techn., Finland, (4) Assoc. EURATOM/CEA, Cadarache, France (5) PPPL, Princeton, USA, (6) Assoc. EURATOM-CIEMAT, Avda Complutense – Madrid, Spain(7) Assoc. Euratom-IPP, MPI fur Plasmaphysik, Garching, Germany (8) Association EURATOM-VR, Fusion Plasma Physics, EES, KTH, 10044 Stockholm, Sweden (9)Assoc. EURATOM/IST, Centro de Fusão Nuclear, Lisbon, Portugal. (10) JAEA Naka, ,Ibaraki-ken, 311-0193 Japan (*) See Appendix of ML Watkins et al., Fusion Energy 2006 (Proc. 21st Int Conf Chengdu, 2006) IAEA, (2006) 1

9. Ripple scan: general results dBT increased pulse by pulse: 0.08% - 0.5% - 0.7% - 1/0% NB absorbed power ~ 12.5 – 13 MW (losses up to 20% PIN) • Main results: • Up to 40% plasma density pump-out ( 30% @dBT = 0.5%) • Ti increases with dBT (up to + 50%) • Te ~ independent • Plasma rotation slows down  VTOR < 0 at the edge at dBT = 1.0% 5

10. 34th European Physical Society Conference on Plasma Physics, Warsaw, July 2-6, 2007 • China ASIPP, 4; SWIP, 2; LFRC，5