PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, 2004 - V. Pericoli Ridolfini et al 1 LHCD and Coupling Experiments with an ITER- like PAM.

Slides:



Advertisements
Similar presentations
Introduction to Plasma-Surface Interactions Lecture 6 Divertors.
Advertisements

First Wall Heat Loads Mike Ulrickson November 15, 2014.
DPP 2006 Reduction of Particle and Heat Transport in HSX with Quasisymmetry J.M. Canik, D.T.Anderson, F.S.B. Anderson, K.M. Likin, J.N. Talmadge, K. Zhai.
LH SOL generated fast particles meeting, Prague, Dec 2004 J. Mailloux JET Programme 2005 Selected issues that could affect LH experiments.
1 G.T. Hoang, 20th IAEA Fusion Energy Conference Euratom Turbulent Particle Transport in Tore Supra G.T. Hoang, J.F. Artaud, C. Bourdelle, X. Garbet and.
H. D. Pacher 1, A. S. Kukushkin 2, G. W. Pacher 3, V. Kotov 4, G. Janeschitz 5, D. Reiter 4, D. Coster 6 1 INRS-EMT, Varennes, Canada; 2 ITER Organization,
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
RF2011, Newport, RI 1 June Long Pulse Operation with the ITER-Relevant LHCD Antenna in Tore Supra A Ekedahl 1, L Delpech 1, M Goniche 1, D Guilhem.
1 Electron Bernstein Wave Research and Plans Gary Taylor Presentation to the 16th NSTX Program Advisory Committee September 9, 2004.
1 ST workshop 2008 Conception of LHCD Experiments on the Spherical Tokamak Globus-M O.N. Shcherbinin, V.V. Dyachenko, M.A. Irzak, S.A. Khitrov A.F.Ioffe.
LHCD Steady-State Technology for KSTAR J. Hosea, S. Bernabei, R. Ellis and J.R. Wilson Presented at the KSTAR Workshop General Atomics, San Diego, CA May.
1 Garching, 20/3 2009EFDA Fuelling Meeting A Ekedahl 1, M Goniche 1, G Granucci 2, J Mailloux 3, V Pericoli 4, V Petrzilka 5, K Rantamäki 6, JET-EFDA contributors,
1 ST workshop 2005 Numerical modeling and experimental study of ICR heating in the spherical tokamak Globus-M O.N.Shcherbinin, F.V.Chernyshev, V.V.Dyachenko,
Association EURATOM-Belgian State LPP-ERM/KMS SCK-CEN ULB M.Van Schoor, V.Massaut, D.Carati.
1 Association Euratom-Cea TORE SUPRA Tore Supra “Fast Particles” Experiments LH SOL Generated Fast Particles Meeting Association Euratom IPP.CR, Prague.
Microstability analysis of e-ITBs in high density FTU plasmas 1)Associazione EURATOM-ENEA sulla fusione, C.R. Frascati, C.P , Frascati, Italy.
Initial Exploration of HHFW Current Drive on NSTX J. Hosea, M. Bell, S. Bernabei, S. Kaye, B. LeBlanc, J. Menard, M. Ono C.K. Phillips, A. Rosenberg, J.R.
1 ITPA St Petersburg April 2009G.Gorini JET results on the determination of thermal/non-thermal fusion yield from neutron emission spectroscopy.
10th ITPA conference, Avila, 7-10 Jan Effects of High Energy Ions Accelerated in front of ICRF Antennas in LHD S. Masuzaki on behalf of the LHD Experimental.
Heating and Current Drive Systems for ARIES-AT T.K. Mau University of California, San Diego ARIES Project Meeting September 18-20, 2000 Princeton Plasma.
Current Drive for FIRE AT-Mode T.K. Mau University of California, San Diego Workshop on Physics Issues for FIRE May 1-3, 2000 Princeton Plasma Physics.
Fyzika tokamaků1: Úvod, opakování1 Tokamak Physics Jan Mlynář 8. Heating and current drive Neutral beam heating and current drive,... to be continued.
RF simulation at ASIPP Bojiang DING Institute of Plasma Physics, Chinese Academy of Sciences Workshop on ITER Simulation, Beijing, May 15-19, 2006 ASIPP.
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
1 Instabilities in the Long Pulse Discharges on the HT-7 X.Gao and HT-7 Team Institute of Plasma Physics, Chinese Academy of Sciences, P.O.Box 1126, Hefei,
Two problems with gas discharges 1.Anomalous skin depth in ICPs 2.Electron diffusion across magnetic fields Problem 1: Density does not peak near the.
1 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
Advances In High Harmonic Fast Wave Heating of NSTX H-mode Plasmas P. M. Ryan, J-W Ahn, G. Chen, D. L. Green, E. F. Jaeger, R. Maingi, J. B. Wilgen - Oak.
1PPPL G. Giruzzi Association Euratom-Cea TORE SUPRA 6/10/2003 Non-linear oscillations and synergy effects in non-inductive plasma regimes on Tore Supra.
ASIPP YOUNIS Jawad, WAN Baonian, LIN Shiyao, SHI Yuejiang, and HT-7 Team HT-7 Study of LHW current drive efficiency and fast electron distribution.
ASIPP Long pulse and high power LHCD plasmas on HT-7 Xu Qiang.
Plasma Facing PFA Antenna Group POLITECNICO DI TORINO 19 Topical Conference on Radio Frequency Power in Plasmas June 1-3, Newport 1 Mitigation of.
Emanuele Poli, 17 th Joint Workshop on ECE and ECRH Deurne, May 7-10, 2012 Assessment of ECCD-Assisted Operation in DEMO Emanuele Poli 1, Emiliano Fable.
ITER STEADY-STATE OPERATIONAL SCENARIOS A.R. Polevoi for ITER IT and HT contributors ITER-SS 1.
D. Tskhakaya, LH SOL Generated Fast Particles Meeting IPP.CR, Prague December 16-17, 2004 Quasi-PIC modelling of electron acceleration in front of the.
FEC 2006 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower.
Steady State Discharge Modeling for KSTAR C. Kessel Princeton Plasma Physics Laboratory US-Korea Workshop - KSTAR Collaborations, 5/19-20/2004.
1 LHCD Properties with a New Lower Hybrid Wave Antenna on HT-7 Tokamak Wei Wei,Guangli Kuang,Bojiang Ding,Weici Shen and HT-7 Team Institute of Plasma.
ASIPP, 24/ Modelling of near LH effects on the SOL, in view of extrapolation to ITER V. Petrzilka 1, G. Corrigan 2, P. Belo 3, A. Ekedahl 4, K.
Euratom TORE SUPRA  CEA comments on documents provided by the Project Leader Introduction I Performance issues II Operation Issues III. Manufacturing.
Microwave emission from the trapped and precipitated electrons in solar bursts J. E. R. Costa and A. C. Rosal1 2005, A&A, 436, 347.
RFX Meeting G. Mazzitelli Padova 21/01/09 Lithization on FTU: tools and results G. Mazzitelli a Many thanks to:M.L. Apicella a, V. Pericoli Ridolfini a,
47th Annual Meeting of the Division of Plasma Physics, October 24-28, 2005, Denver, Colorado ECE spectrum of HSX plasma at 0.5 T K.M.Likin, H.J.Lu, D.T.Anderson,
Page 1 Alberto Loarte- NSTX Research Forum st - 3 rd December 2009  ELM control by RMP is foreseen in ITER to suppress or reduce size of ELM energy.
47th Annual Meeting of the Division of Plasma Physics, October 24-28, 2005, Denver, Colorado 1 Tesla Operation of the HSX Stellarator Simon Anderson, A.Almagri,
Quasi-linear Formalism for Simulation of Electron Cyclotron Current Drive Z. T. Wang, Y. X. Long, J.Q. Dong, F. Zonca Southwestern Institute of Physics,
APS, 44th Annual Meeting of the Division of Plasma Physics November 11-15, 2002; Orlando, Florida Hard X-ray Diagnostics in the HSX A. E. Abdou, A. F.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
5.4 Stored Energy Crashes  Diamagnetic loop shows the plasma energy crashes at low plasma density  ECE signals are in phase with the energy crashes 
Current Drive Experiments with Oscillating Toroidal Flux in HT-7 Superconducting Tokamak J.S.Mao, P. Phillips 1, J.R.Luo, J.Y.Zhao, Q.L.Wu, Z.W.Wu, J.G.Li,
HT-7 Proposal of the investigation on the m=1 mode oscillations in LHCD Plasmas on HT-7 Exp2005 ASIPP Youwen Sun, Baonian Wan and the MHD Team Institute.
Institute of Plasma Physics, Chinese Academy of Sciences Challenge in LHCD capability at high density regime B J Ding, M H Li, J G Li and B N Wan for EAST.
Lower Hybrid Wave Coupling and Current Drive Experiments in HT-7 Tokamak Weici Shen Jiafang Shan Handong Xu Min Jiang HT-7 Team Institute of Plasma Physics,
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
= 2·10 18 m -3 T e (0) = 0.4 keV ECH and ECE on HSX Stellarator K.M.Likin, A.F.Almagri, D.T.Anderson, F.S.B.Anderson, C.Deng 1, C.W.Domier 2, R.W.Harvey.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
1 Radiation Environment at Final Optics of HAPL Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI HAPL Meeting ORNL March.
48th Annual Meeting of the Division of Plasma Physics, October 30 – November 3, 2006, Philadelphia, Pennsylvania Energetic-Electron-Driven Alfvénic Modes.
9-12 Sept. 2002E. BARBAT0-ENEA, TTF, Cordoba1 Electron Internal Transport barriers by LHCD and ECRH in FTU-high density plasmas E. Barbato Associazione.
SAWTOOTH AND M=1 MODE BEHAVIOUR IN FTU PELLET ENHANCED DISCHARGES
Zhouqian, Wan baonian and spectroscopy team
JongGab Jo, H. Y. Lee, Y. H. An, K. J. Chung and Y. S. Hwang*
Associazione EURATOM-ENEA sulla Fusione
LH Generated Hot Spots on the JET Divertor
A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, H. St John
First Experiments Testing the Working Hypothesis in HSX:
The Gas Dynamic Trap (GDT) Neutron Source
20th IAEA Fusion Energy Conference,
Progress towards development of long pulse ITER operation trough RF heated H-mode experiments in EAST and HL-2A (A. Ekedahl et al., EX/P2-16)
Presentation transcript:

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 1 LHCD and Coupling Experiments with an ITER- like PAM launcher on the FTU tokamak V. Pericoli Ridolfini, M.L. Apicella, E. Barbato, Ph. Bibet 1, P. Buratti, G. Calabrò, A. Cardinali, G. Granucci 2, F. Mirizzi, L. Panaccione, S. Podda, C. Sozzi 2, A.A. Tuccillo Associazione EURATOM-ENEA sulla Fusione, C.R. FRASCATI (Roma), Italy 1 Association Euratom CEA sur la Fusion, CEA Cadarache, France 2 Associazione EURATOM-ENEA-CNR sulla Fusione, IFP-CNR, Milano, Italy Experiment conducted jointly with CEA in the frame of the ENEA - CEA collaboration on electron dynamics studies

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 2 Why a Passive/Active Multijunction Launcher? Robust LH launchers to face the harsh plasma environment of ITER: Strong stresses ≈100 MPa Thick vertical walls between active waveguides  neutron flux ≈0.5 MW/m 2 (13.25 mm) cooling system in the walls Passive (short-circuited) waveguides at the mouth (within the thick walls, depth= /4), to restore the usual multijunction periodicity Main requests for a PAM 1)To maintain good coupling even operating in the full shadow of the vessel port to avoid damage from the large particle flow inside the SOL plasma 2)To tolerate the heating due to the neutron flux and plasma radiation losses 3)To preserve power handling and CD efficiency acceptable for ITER FTU experiment was aimed to validate the PAM concept through testing mainly points 1 & 3 (coupling and CD)

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 3 12 MJs in a 4x3 matrix Waveguides: 28x5 mm Frequency : f=8 GHz Design power=80 MW/m 2 ITER: waveguides: 58x9.25 mm f=5 GHz power = 33 MW/m 2 The experimental scaling of power handling, linear with f : 33 MW/m 2 in ITER  52 MW/m 2 in FTU FTU PAM view and layout PAM module 76 mm

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 4 Obtained with R c < 1.6 %: 80 MW/m 2 (design value) with 200/80 ms ON/OFF modulation 75 MW/m 2 for t>0.9 s, quasi steady, limited only by power sources ITER equivalent: 52 MW/m 2 > 90 MW/m 2 attainable with further conditioning

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 5 PAM / Conventional grill power coupling Good coupling always for n e ≥ n e,cut-off : R c ≤1.5% and decreasing with n e GRILL-3D foresees the rise close to n e,cut-off Conv. grill cannot operate at low n e M. Irzak, O. Schcherbinin, Nucl. Fus. 35, 1341 (1995)

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 6 Current Drive capability Same N ||,pk =2.24 for PAM and conventional grill PAM  CD smaller due -) lower directivity: 65% against 80% -) lower nene V loop I LH /I p P LH

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 7 CD performances on many shots basis  : incremental effect of PAM onto conven. grill N || spectra Non-linearity at low h, due to low power / low collisionality reduced by considering directivities

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 8 Comparing PAM  CD with FTU data base PAM and conventional grill behave very similarly either alone or together The effects are additive  CD grows with : points are aligned with FTU data base

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 9 Amount of the fast e - population PAM/Conv. All data points consistent (i.e. PAM, Conv., PAM+Conv.) for both ECE and HXR if is taken as the main guiding parameter as for  CD Hard X-rays ECE

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 10 Varying PAM N ||,pk - Hard X-rays Same V loop for both discharges Fast tail more developed for the faster spectrum E=80 keV  c/v e =1.85 (effect larger when PAM is alone) PAM can change its N ||

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 11 Comparing different N ||,pk - ECE Ratio of more to less energetic e - emission higher for faster N || spectra  227 (a/2)=1.43  297 (a/2)=1.09 N || =1.4 N || =2.5 ECE spectra ECE signal ratio PAM does have some flexibility in N ||

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 12 Hard X ray radial profiles ( keV) Lower densities -> profiles broader: fast e - radial diffusion Some differences due to N || spectra seen on HXR profiles Consistency with calculated LH deposition (ASTRA) in: E. Barbato, EPS London 2004 P2.104

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 13 PAM coupling - modification of the edge Building-up of density in front of the mouth Large R c (outgassing) => low n e and low ECE power absorbed inside w.g.? Note: n e ≤ n e,cut-off before the LH pulse R PAM =-2 mm Note: n e ≤ n e,cut-off before the LH pulse R PAM =-2 mm Need of good conditioning

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 14 Conclusions - I The test of the PAM at FTU has been successful: -Good coupling achieved with density close to or at the cut-off and antenna retracted up to 3 mm inside the port -Power more than 1.4 times that required for ITER safely managed in quasi steady state: Actual values in FTU: 75 MW/m 2 (=> 250 kW total) Request scaled from ITER: 53 MW/m 2 (=>170 kW total) - Good current drive efficiency is maintained

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 15 Conclusions - II -Actual power limit can be even exceeded with further conditioning (>90 MW/m 2 possible) -PAM and Conventional grill produce very similar CD and heating effects (considering the different directivities) and fast e - tails (from HXR and ECE signals) -Flexibility in N || with  (phase difference bwtween adjacent modules) found from both HXR and ECE The first step towards developing an ITER LHCD launcher has been succesful

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 16 Comparing different N ||,pk PAM - CD N ||,pk =2.4 (  PAM =180°), directivity 65% P LH =240kW N ||,pk =1.7 (  PAM =0°), directivity 53% P LH =195 kW Same V loop =>  CD higher for N ||,pk =1.7 }

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 17 HXR emission simulation HXR spectra calculation consistent with experiment Assumptions: e - distribution function with a fast tail in 3.5v th,e <w<c/N ||,pk Fraction of fast e - (≈1‰) to account for the driven current LH power deposition from a Bonoli-type code

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 18 Comparison HXR profiles /calculated LH deposition ASTRA + Fast ray tracing E. Barbato, EPS London 2004 P2.104 PAM+Conv.grill n e ≈5·10 19 m -3

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 19 The proposed LHCD System for ITER

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 20 The ITER LHCD launcher Power Spectrum (computed)

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 21 Layout of a PAM module(top view) The launcher is longitudinally split in two parts: the first part contains the E–plane bi–junctions and 90° phase shifters in every other waveguide, the second part is the mouth with the passive waveguides and additional 180° phase shifters to have the required 270° between the two active waveguides of each module.

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 22 FTU PAM test Mechanical dimensions determined by the cross-section of the FTU port (400  80 mm 2 ): Cross section of the waveguides:28  5 mm 2 Wall thickness (mouth):0.8 mm Depth of passive waveguides: mm Phase pitch (active waveguides): 270° N || peak (phase betw. modules  = 180°):2.4 N || (  = ±180°):1.6÷2.9 The PAM launcher has replaced the upper conventional grill (CG) of the launching structure installed in the port no. 10 of FTU. To operate with the same value of N || (N || = 2.2), the feeding phase between adjacent toroidally PAM modules has been set to 135° and to 110° between toroidally adjacent waveguides in the CG. The expected power directivity at twice the cut-off electron density (n ec = m -3 ) is respectively 65% for the PAM and 80% for the CG.

PAM experiment on FTU (EX/5-5) - 20 th FEC.Villamoura 1-6 Nov, V. Pericoli Ridolfini et al 23 Experimental scaling of power in waveguides Power safely managed with a phased waveguide antenna as it results from comparison between many tokamaks M. Aquilini et al., Fusion Sci. & Techn. V. 45, p. 459 (May 2004)