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 on 34th 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. 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 Parallel invited talks on 34th EPS Conference on Plasma Physics

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  I Coil ≤ 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. Reduction in ELM energy loss  W/W without n = 1 fieldwith n = 1 field #67954 16.60 16.66 16.72 Time (s) #67959 17.78 17.79 17.80 Time (s) DD DD W Dia  W/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  BT increased pulse by pulse: 0.08% - 0.5% - 0.7% - 1/0% NB absorbed power ~ 12.5 – 13 MW (losses up to 20% P IN ) Main results:  Up to 40% plasma density pump-out ( 30% @  BT = 0.5%)  T i increases with  BT (up to + 50%)  T e ~ independent  Plasma rotation slows down  V TOR < 0 at the edge at  BT = 1.0% 5

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