HHFW heating experiments in NSTX S. Bernabei, J. Hosea, B. LeBlanc, C. K. Phillips, P. Ryan, D. Swain, J. R. Wilson and the whole NSTX crew. ORNL.

Slides:



Advertisements
Similar presentations
Anomalous Ion Heating Status and Research Plan
Advertisements

NSTX Reflectometer Measurements of RF Waves in the Scrape-off Layer in Front of the HHFW Antenna Array J. B. Wilgen, G. R. Hanson, P. M. Ryan, D. W. Swain.
Session A Wrap Up. He Abundance J. Kasper Helium abundance variation over the solar cycle, latitude and with solar wind speed Slow solar wind appears.
STATUS OF THE HHFW CURRENT DRIVE EXPERIMENT ON NSTX Phil Ryan, Randy Wilson, David Swain, Bob Pinsker March 3, 2004 run date. This XP is focused on CD.
Physics of fusion power Lecture 10 : Running a discharge / diagnostics.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
F. Cheung, A. Samarian, W. Tsang, B. James School of Physics, University of Sydney, NSW 2006, Australia.
Physics of fusion power Lecture 7: particle motion.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
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.
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,
Kinetic Effects on the Linear and Nonlinear Stability Properties of Field- Reversed Configurations E. V. Belova PPPL 2003 APS DPP Meeting, October 2003.
1 Association Euratom-Cea TORE SUPRA Tore Supra “Fast Particles” Experiments LH SOL Generated Fast Particles Meeting Association Euratom IPP.CR, Prague.
Profile Measurement of HSX Plasma Using Thomson Scattering K. Zhai, F.S.B. Anderson, J. Canik, K. Likin, K. J. Willis, D.T. Anderson, HSX Plasma Laboratory,
J A Snipes, 6 th ITPA MHD Topical Group Meeting, Tarragona, Spain 4 – 6 July 2005 TAE Damping Rates on Alcator C-Mod Compared with Nova-K J A Snipes *,
1 JBW-NSTX 9/10/02 Reflectometer Measurements of the Plasma Edge in front of the HHFW antennas John Wilgen, David Swain, Greg Hanson, Phil Ryan Oak Ridge.
XP NSTX Results Review Beam Modulation Effects on Ion Power Balance XP 737 P.W.Ross.
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 CHI Summary Transient CHI (XP606) –All systems operated reliably without any faults Edge Current drive (XP533)
J.R. Wilson, R.E. Bell, S. Bernabei, T. Biewer, J. C. Hosea, B. LeBlanc, M. Ono, C. K. Phillips Princeton Plasma Physics Laboratory P. Ryan, D.W Swain.
Mid-Run Assessment - ISD S. Kaye, D. Gates 10 May 2006.
V. A. Soukhanovskii 1 Acknowledgement s: R. Maingi 2, D. A. Gates 3, J. Menard 3, R. Raman 4, R. E. Bell 3, C. E. Bush 2, R. Kaita 3, H. W. Kugel 3, B.
Rotation effects in MGI rapid shutdown simulations V.A. Izzo, P.B. Parks, D. Shiraki, N. Eidietis, E. Hollmann, N. Commaux TSD Workshop 2015 Princeton,
NSTX-U NSTX-U PAC-31 Response to Questions – Day 1 Summary of Answers Q: Maximum pulse length at 1MA, 0.75T, 1 st year parameters? –A1: Full 5 seconds.
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.
Supported by Office of Science Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U.
ARIES-AT Physics Overview presented by S.C. Jardin with input from C. Kessel, T. K. Mau, R. Miller, and the ARIES team US/Japan Workshop on Fusion Power.
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 Confinement Studies on TJ-II Stellarator with OH Induced Current F. Castejón, D. López-Bruna, T. Estrada, J. Romero and E. Ascasíbar Laboratorio Nacional.
Nonlinear Optics in Plasmas. What is relativistic self-guiding? Ponderomotive self-channeling resulting from expulsion of electrons on axis Relativistic.
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.
ASIPP Long pulse and high power LHCD plasmas on HT-7 Xu Qiang.
CHI Run Summary for March 10-12, 31 & April 9, 2008 Flux savings from inductive drive of a Transient CHI started plasma (XP817) R. Raman, B.A. Nelson,
NSTX EXPERIMENTAL PROPOSAL - OP-XP-825 Title: HHFW Heating/CD phase scans in D L-mode plasmas P. Ryan, J. Hosea, R. Bell, L. Delgado-Aparicio, S. Kubota,
Transport in three-dimensional magnetic field: examples from JT-60U and LHD Katsumi Ida and LHD experiment group and JT-60 group 14th IEA-RFP Workshop.
ASIPP HT-7 The effect of alleviating the heat load of the first wall by impurity injection The effect of alleviating the heat load of the first wall by.
EFDA EUROPEAN FUSION DEVELOPMENT AGREEMENT Task Force S1 J.Ongena 19th IAEA Fusion Energy Conference, Lyon Towards the realization on JET of an.
STUDIES OF NONLINEAR RESISTIVE AND EXTENDED MHD IN ADVANCED TOKAMAKS USING THE NIMROD CODE D. D. Schnack*, T. A. Gianakon**, S. E. Kruger*, and A. Tarditi*
NSTX HIGH HARMONIC FAST WAVE CALCULATIONS
HL-2A Heating & Current Driving by LHW and ECW study on HL-2A Bai Xingyu, HL-2A heating team.
Exploration of High Harmonic Fast Wave Heating on NSTX J. R. Wilson 2002 APS Division of Plasma Physics Meeting November 11-15, 2002 Orlando, Florida.
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.
1 Stability Studies Plans (FY11) E. Fredrickson, For the NCSX Team NCSX Research Forum Dec. 7, 2006 NCSX.
1 EBW & HHFW Research - G. Taylor PAC-19 2/23/06 EBW & HHFW Research (Including EBW Collaborations with MAST & P EGASUS ) Gary Taylor presented on behalf.
The influence of non-resonant perturbation fields: Modelling results and Proposals for TEXTOR experiments S. Günter, V. Igochine, K. Lackner, Q. Yu IPP.
Summary of RF-Related Presentations at the 2011 EPS Meeting G. Taylor NSTX Physics Meeting July 25, 2011 NSTX Supported by 1.
Dependence of Pedestal Structure on Ip and Bt A. Diallo, R. Maingi, S. Zweben, B.P. LeBlanc, B. Stratton, J. Menard, S. Gerhardt, J. Canick, A. McClean,
1 DWS- NSTX Results Review Sept02 Power and Voltage Limits in the NSTX Ion Cyclotron System* David Swain NSTX Results Review Meeting PPPL September 9 –
Solenoid Free Plasma Start-up Mid-Run Summary (FY 2008) R. Raman and D. Mueller Univ. of Wash. / PPPL 16 April 2008, PPPL 1 Supported by Office of Science.
1Field-Aligned SOL Losses of HHFW Power and RF Rectification in the Divertor of NSTX, R. Perkins, 11/05/2015 R. J. Perkins 1, J. C. Hosea 1, M. A. Jaworski.
Characterization of Fast Ion Power Absorption of HHFW in NSTX A. Rosenberg, J. Menard, J.R. Wilson, S. Medley, R. Dumont, B.P. LeBlanc, C.K. Phillips,
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,
FY WEP TSG Goals & WEP-Relevant Diagnostic Upgrades NSTX Supported by WEP TSG Meeting September 14,
1 NSTX EXPERIMENTAL PROPOSAL - OP-XP-712 Title: HHFW Power Balance Optimization at High B Field J. Hosea, R. Bell, S. Bernabei, L. Delgado-Aparicio, S.
T. Biewer, March 3 rd, 2003NSTX Physics Meeting Measurements of Edge Impurity Ion Dynamics During RF Heating T. M. Biewer, R.E. Bell March 3 rd, 2003 NSTX.
Development and Assessment of “X-point limiter” Plasmas M. Bell, R. Maingi, K-C. Lee Coping with both steady-state and transient (ELM) heat loads is a.
Simulation of Non-Solenoidal Current Rampup in NSTX C. E. Kessel and NSTX Team Princeton Plasma Physics Laboratory APS-DPP Annual Meeting, Savannah, Georgia,
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 
1 ASIPP Sawtooth Stabilization by Barely Trapped Energetic Electrons Produced by ECRH Zhou Deng, Wang Shaojie, Zhang Cheng Institute of Plasma Physics,
NSTX APS-DPP: SD/SMKNov Abstract The transport properties of NSTX plasmas obtained during the 2008 experimental campaign have been studied and.
Long Pulse High Performance Plasma Scenario Development for NSTX C. Kessel and S. Kaye - providing TRANSP runs of specific discharges S.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
Soft X-Ray Tomography in HSX V. Sakaguchi, A.F. Almagri, D.T. Anderson, F.S.B. Anderson, K. Likin & the HSX Team The HSX Plasma Laboratory University of.
T. Biewer, Sep. 20 th, 2004 NSTX Results Review of 11 Edge Ion Heating by Launched HHFW in NSTX T.M. Biewer, R.E. Bell, S. Diem, P.M. Ryan, J.R.
Features of Divertor Plasmas in W7-AS
First Experiments Testing the Working Hypothesis in HSX:
Near-Field Physics of Lower-Hybrid Wave Coupling to Long-Pulse, High Temperature Plasmas in Tore Supra A dynamic Stark effect measurement performed near.
No ELM, Small ELM and Large ELM Strawman Scenarios
Presentation transcript:

HHFW heating experiments in NSTX S. Bernabei, J. Hosea, B. LeBlanc, C. K. Phillips, P. Ryan, D. Swain, J. R. Wilson and the whole NSTX crew. ORNL

Outline of results HHFW has several goals for NSTX physics: current drive to extend the pulse plasma heating plasma startup and other. Electron heating can be rather efficient depending on the phase of the antenna. There are some indications of current drive, but in general somewhat disappointing HHFW achieves H-mode. But several puzzles remain and need to be addressed theoretically and experimentally. 1

COUPLING 2 Co-CD = 0 -  1/2)   - (3/2)  = -90° Cntr-CD = 0 +  1/2)   +(3/2)  = +90° Superdipole = 0 0   0 0 Dipole = 0  0  0  = 180°

Heating efficiency depends on the plasma edge conditions especially from “inner gap”. Apparently the relevant parameter is plasma shape and position 3

heating efficiency  E/P inversely proportional to loading loading depends on phase loading independent of plasma density Loading increases with power: could ponderomotive effects “push” the plasma away and so increasing coupling to surface waves? LOADING - COUPLING -----> HEATING 4  E/P

180° has best heating t=0.22 there is MHD) -90° has very high D  -90° reflected power shows no time variation +90° has intermediate behaviour 1 THESE FINDINGS POINT TO A DEGREE OF POWER COUPLED TO SURFACE WAVES, ESPECIALLY FOR -90° (CO-CD) 2 HIGH LOADING DOES NOT NECESSARILY MEAN EFFICIENT COUPLING TO CORE PLASMA -90° +90° 180° Edge phenomena show phase dependence and coupling to surface waves 5

Heating efficiency decreases with k || 180° has higher power absorption (80%) +90° (counter CD) is more efficient than -90° (co-CD) Power at -30° (theoretically the most efficient at driving current) has very small absorption Part of the missing power from the core is radiated to the wall (larger for low k || ) Modulation experiments were performed in order to obtain the percentage of RF power absorbed in the plasma. +30° -90° +90° 180° MODULATION EXPERIMENTS 6

total stored energy Derivation of  E and  at four times (t o ) o E ~ E +  E (1- exp[-(t-t o )/  ] % (pwr. abs.) =  E/(P  ) curve fit o time RF power t o = EE 

% of absorbed power in Helium Different symbol corresponds to different shot As seen before,  =180° heats better that  =-90° This means that a good portion of the power launched at -90° is not penetrating in the plasma core and dissipated in excitation of parametric instabilities and (possibly) in surface waves 8

Tau in Helium Stronger heating and lower confinemet time, make absorption of waves at 180° higher than waves at -90° The lower confinement time for 180° is baffling: one possible explanation is that 180° damps at low electron temperature ( eV), therefore off-axis, with consequent low confinement time. (see page 13) 9 -90° 180°

% of absorbed power in Deuterium Deuterium data were not as clean as in Helium Still 180° and +90° show higher values of absorption than -90° -30°, which theoretically should give high current drive efficiency, shows <20% absorption 10

Tau in Deuterium The higher percentage of power absorbed at +90° appears to by due to the lower confinemet time. This is a puzzle which needs to be understood. 11

Two modes: both with n=1 (and m=1 or m=2) both responsible for heating saturation and losses (the possible explanation for its destabilization is discussed in the next section) Low frequency MHD during heating 12

good heating at 180° increase of q o decreasing of l i = broadening red RF power (black: shot at -90° at lower power, used as reference in absence of a no-RF shot) MHD Indications of current profile broadening at 180° Is this direct current drive generated by RF power or Bootstrap? 13

q-profile modified during RF with  = 180° power = 2.0 MW phase = 180° This is consistent with: 1 off-axis heating (see TS) 2 decrease of l i 3 increase of q o 4 destabilization of MHD modes Reconstruction of the q- profiles before RF at t=0.15 sec and after 60 ms (t=0.21) shows a broadening around q=2 14 (see poster)

broad Thomson scattering profiles for  =180° MHD nene T eo RF power IpIp profiles at t=0.15 before RF profiles at t=0.21 before MHD 15

MHD for the same three shots shown at page 5 The three shots have same net power. A strong mode is seen at 180°; weaker at +90° and absent at -90° Even if the power absorption for - 90° is smaller than for 180°, the threshold for MHD destabilization is smaller for 180° ( 1 MW) than for -90°. +90° is intermediate. 16

Like in the early LH experiments, in which it was assumed that LH was responsible for MHD instabilities, during application of HHFW power it is NOT the RF power that excites MHD, but it is rather the current profile change due to RF power that excites MHD. Therefore every observation is consistent with a broadening of the current profile during HHFW at  =180° (direct RF or bootstrap ?) which causes a steepening of the profile around q=2. Note from the Coupling figure that, because of the strong tilt of the field lines, 180° does not produce a symmetric spectrum. In addition there is a strong residual electric field which augments the asymmetry.  -90° has much smaller effect, while +90° an intermediate one: This could be due to the lower absorption efficiency. 17 But it might also indicate that higher k || are required for current drive. gkgh

HEATING SCALINGS Example of power fit for t exp vs. total power All the shots are included in the two plots on the left, vs. H-mode scaling and L thermal scaling. The points fall samewhat in between. 18

Confinement trends point toward moderate I p and maximum B T Each point represents a shot: spread is due to power. Only shots with power between 1 MW and 2 MW are plotted. 19

Summary HHFW heats electrons: heating efficiency ranges from ~80% to ~20% and is strongly proportional to k ||. (see CO J. R. Wilson) An important parameter for this disparity in power absorption with different k || appears to be due to the plasma conditions in front of the antenna (density, shape and possibly geometry). Low k || seem to dissipate part of the power in parametric instabilities and surface waves. (see JP1.014 S. Diem) Looking at the power dissipated in parametric waves and to the radiated power we are not yet able to account for all the power that is launched in the vessel Difference between -90° and +90° is a puzzle. MHD modes, either (1,1) or (2,1), cause degradation of the heating efficiency. They appear to be caused by current profile change. Heating scaling falls somewhat in between H-mode and L thermal scaling 20 (see also JP1.009 LeBlanc, JP1.012 Hosea, JP Phillips, CO3.013 P. Ryan)

Proposed experiments  Reverse the magnetic field to determine if the difference between -90° and +90° is due to geometrical constraint.  Use edge probes, surface reflectometer, Rogowski coils between plates and wall to determine if (and how much) RF power is coupled to surface waves and dissipated in sheaths.  Change edge conditions and configuration to understand coupling.  Complete modulation experiments, varying phase (power? Ip? B? ne?) and gas (Deuterium data were not very good).  Use X-ray diagnostics perpendicular and parallel to look for asymmetry in the electron distribution in the z-direction (CD?) 21

The first author, would welcome very much constructive comments; please direct any criticism to the