53rd Annual Meeting of the Division of Plasma Physics, November 14 - 18, 2010, Salt Lake City, Utah 5-pin Langmuir probe configured to measure the Reynolds.

Slides:



Advertisements
Similar presentations
Self-consistent mean field forces in two-fluid models of turbulent plasmas C. C. Hegna University of Wisconsin Madison, WI Hall Dynamo Get-together PPPL.
Advertisements

Self-consistent mean field forces in two-fluid models of turbulent plasmas C. C. Hegna University of Wisconsin Madison, WI CMSO Meeting Madison, WI August.
Momentum Transport During Reconnection Events in the MST Reversed Field Pinch Alexey Kuritsyn In collaboration with A.F. Almagri, D.L. Brower, W.X. Ding,
FEC 2004 Measurements and Modeling of Plasma Flow Damping in the HSX Stellarator S.P. Gerhardt, A.F. Almagri, D.T. Anderson, F.S.B. Anderson, D. Brower,
Two-dimensional Structure and Particle Pinch in a Tokamak H-mode
Inter-ELM Edge Profile and Ion Transport Evolution on DIII-D John-Patrick Floyd, W. M. Stacey, S. Mellard (Georgia Tech), and R. J. Groebner (General Atomics)
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.
Institut für Plasmaforschung Universität Stuttgart Long-distance correlation of fluctuations under strong ExB shear in TJ-K P. Manz, M. Ramisch, U. Stroth.
Reduced transport regions in rotating tokamak plasmas Michael Barnes University of Oxford Culham Centre for Fusion Energy Michael Barnes University of.
Paper O4.007, R. A. Pitts et al., 34th EPS Conference: 5 July 2007 Neoclassical and transport driven parallel SOL flows on TCV R. A. Pitts, J. Horacek.
Plasma Characterisation Using Combined Mach/Triple Probe Techniques W. M. Solomon, M. G. Shats Plasma Research Laboratory Research School of Physical Sciences.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
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.
N=4,m=0 n=4,m=1 n=8,m=0 The HSX Experimental Program Program F. Simon B. Anderson, D.T. Anderson, A.R. Briesemeister, C. Clark, K.M.Likin, J. Lore, H.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
N EOCLASSICAL T OROIDAL A NGULAR M OMENTUM T RANSPORT IN A R OTATING I MPURE P LASMA S. Newton & P. Helander This work was funded jointly by EURATOM and.
Parallel and Poloidal Sheared Flows close to Instability Threshold in the TJ-II Stellarator M. A. Pedrosa, C. Hidalgo, B. Gonçalves*, E. Ascasibar, T.
Edge Localized Modes propagation and fluctuations in the JET SOL region presented by Bruno Gonçalves EURATOM/IST, Portugal.
30 th EPS conference, St. Petersburg, Russia, July, 7-11, 2003 K.M.Likin On behalf of HSX Team University of Wisconsin-Madison, USA Comparison of Electron.
Plasma Dynamics Lab HIBP E ~ 0 V/m in Locked Discharges Average potential ~ 580 V  ~ V less than in standard rotating plasmas Drop in potential.
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.
49th Annual Meeting of the Division of Plasma Physics, November 12 – November 16, 2007, Orlando, Florida Ion Species: Cs-133 Initial Energy: 10 keV Launch.
SLM 2/29/2000 WAH 13 Mar NBI Driven Neoclassical Effects W. A. Houlberg ORNL K.C. Shaing, J.D. Callen U. Wis-Madison NSTX Meeting 25 March 2002.
HT-7 ASIPP The Influence of Neutral Particles on Edge Turbulence and Confinement in the HT-7 Tokamak Mei Song, B. N. Wan, G. S. Xu, B. L. Ling, C. F. Li.
EXTENSIONS OF NEOCLASSICAL ROTATION THEORY & COMPARISON WITH EXPERIMENT W.M. Stacey 1 & C. Bae, Georgia Tech Wayne Solomon, Princeton TTF2013, Santa Rosa,
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.
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.
52 nd APS-DPP Annual Meeting, November, 8-12, 2010, Chicago, IL Plasma Pressure / BJ Contours Poloidal dimension Radial dimension Toroidal Angle (rad)
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois Non-symmetric components were intentionally added to the.
1) For equivalent ECRH power, off-axis heating results in lower stored energy and lower core temperature 2) Plasma flow is significantly reduced with off-axis.
Measurements of Magnetic Fluctuations in HSX S. Oh, A.F. Almagri, D.T. Anderson, C. Deng, C. Lechte, K.M. Likin, J.N. Talmadge, J. Schmitt HSX Plasma Laboratory,
Helically Symmetry Configuration Evidence for Alfvénic Fluctuations in Quasi-Helically Symmetric HSX Plasmas C. Deng and D.L. Brower, University of California,
51 st APS-DPP Annual Meeting, 2-6 November 2009, Atlanta GA Time BθBθ Φ≈ 1/6 FP Φ≈1/2 FP J Pfirsh-Schlüter Poloidal Index BθBθ.
52nd Annual Meeting of the Division of Plasma Physics, November , 2010, Chicago, Illinois 5-pin Langmuir probe configured to measure floating potential.
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
Simulation of Turbulence in FTU M. Romanelli, M De Benedetti, A Thyagaraja* *UKAEA, Culham Sciance Centre, UK Associazione.
1 Recent Progress on QPS D. A. Spong, D.J. Strickler, J. F. Lyon, M. J. Cole, B. E. Nelson, A. S. Ware, D. E. Williamson Improved coil design (see recent.
53rd Annual Meeting of the Division of Plasma Physics, November 13 – November 18, 2011, Salt Lake City, UT Laser Blow-Off Impurity Injection Experiments.
IAEA-TM 02/03/2005 1G. Falchetto DRFC, CEA-Cadarache Association EURATOM-CEA NON-LINEAR FLUID SIMULATIONS of THE EFFECT of ROTATION on ION HEAT TURBULENT.
= Boozer g= 2*1e -7 *48*14*5361 =.7205 =0 in net current free stellarator, but not a tokamak. QHS Mirror Predicted Separatrix Position Measurements and.
51st Annual Meeting of the Division of Plasma Physics, November 2 - 6, 2009, Atlanta, Georgia ∆I BS = 170 Amps J BS e-root J BS i-root Multiple ambipolar.
Plasma Turbulence in the HSX Stellarator Experiment and Probes C. Lechte, W. Guttenfelder, K. Likin, J.N. Talmadge, D.T. Anderson HSX Plasma Laboratory,
Plan V. Rozhansky, E. Kaveeva St.Petersburg State Polytechnical University, , Polytechnicheskaya 29, St.Petersburg, Russia Poloidal and Toroidal.
Bootstrap current in quasi-symmetric stellarators Andrew Ware University of Montana Collaborators: D. A. Spong, L. A. Berry, S. P. Hirshman, J. F. Lyon,
56th Annual Meeting of the Division of Plasma Physics, October 27 – October 31, 2014, New Orleans, LA Increase ion temperature with neutral beams: Study.
Flows Move Primarily Along the Helical Direction of Symmetry Geometric factors are used to relate the measured velocities to the average flow in the symmetry.
18 th Int’l Stellarator/Heliotron Workshop, 29 Jan. – 3 Feb. 2012, Canberra – Murramarang Reserve, Australia Recent Results and New Directions of the HSX.
56 th Annual Meeting of the Division of Plasma Physics. October 27-31, New Orleans, LA Using the single reservoir model [3], shown on right, to:
54 th APS-DPP Annual Meeting, October 29 - November 2, 2012, Providence, RI Study of ICRH and Ion Confinement in the HSX Stellarator K. M. Likin, S. Murakami.
57th Annual Meeting of the Division of Plasma Physics, November , Savannah, Georgia Equilibrium Reconstruction Theory and Modeling Optimized.
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
54th Annual Meeting of the Division of Plasma Physics, October 29 – November 2, 2012, Providence, Rhode Island 5-pin Langmuir probe measures floating potential.
48th Annual Meeting of the Division of Plasma Physics, October 30 – November 3, 2006, Philadelphia, Pennsylvania Energetic-Electron-Driven Alfvénic Modes.
48th Annual Meeting of the Division of Plasma Physics, October 30 – November 3, 2006, Philadelphia, Pennsylvania HIBP Designs for Measurement of the Electric.
Measurements of Reynolds stress flow drive and radial electric fields in the edge of HSX Bob Wilcox HSX Plasma Laboratory University of Wisconsin, Madison.
Neoclassical Currents and Transport Studies in HSX at 1 T
Neoclassical Predictions of ‘Electron Root’ Plasmas at HSX
J.C. Schmitt, J.N. Talmadge, J. Lore
Carlos Hidalgo Laboratorio Nacional de Fusión CIEMAT Madrid, Spain
Modeling Neutral Hydrogen in the HSX Stellarator
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik1, D.L. Brower2, C. Deng2,
Spontaneous rotation in stellarator and tokamak
Magnetic fluctuation measurements in HSX and its impact on transport
Impurity Transport Research at the HSX Stellarator
Characteristics of Biased Electrode Discharges in HSX
Characteristics of Edge Turbulence in HSX
Studies of Bias Induced Plasma Flows in HSX
First Experiments Testing the Working Hypothesis in HSX:
Targeted Physics Optimization in HSX
Presentation transcript:

53rd Annual Meeting of the Division of Plasma Physics, November , 2010, Salt Lake City, Utah 5-pin Langmuir probe configured to measure the Reynolds stress using local floating potential and ion saturation current measurements Tungsten probe tips insulated by boron nitride Signals sampled at 5 MHz Probes scanned radially on a shot-by-shot basis Three pins measure floating potential to infer E r and E θ for calculation of local plasma ExB velocities Two pins measuring ion saturation current are configured as a mach probe and aligned on a field line to measure V ||. Measurements of Reynolds stress flow drive using Langmuir probes in HSX R.S. Wilcox 1, J.A. Alonso 2, D. Carralero 2, J.N. Talmadge 1, D.T. Anderson 1, F.S.B. Anderson 1 1 HSX Plasma Laboratory, University of Wisconsin, Madison, USA 2 Asociación EURATOM-CIEMAT, Madrid, Spain Reynolds Stress and Flow Measurements Langmuir Probe Configuration References 1) R. S. Wilcox et al., Nucl. Fusion 51 (2011) ) D.A. Spong, Phys. Plasmas 12 (2005) ) G. Tynan et al., Plasma Phys. Control. Fusion 48 (2006) S51. 4) M. Coronado and H. Wobig, Phys. Fluids B 29 (1986) 527. Indications of zonal flows have been observed in HSX during biasing in previous experiments [1] A Langmuir probe configuration designed to measure the Reynolds stress has been designed and implemented to measure the mean and fluctuating values of E r, E θ, and v ||. A radial Reynolds stress profile is measured on a shot-to-shot basis using similar discharges Neoclassical poloidal viscosity is calculated to estimate the poloidal flow expected from the measured Reynolds stress gradient, and this is compared to the actual measured E r profile The flow drive calculated this way is large enough to drive significant flows, and radial regions of large flow drive correspond with regions where the measured radial electric field deviates significantly from the neoclassically predicted value given by the PENTA code [2]. When a bias is applied, the fluctuations are reduced by the shearing of the radial electric field and the poloidal flow is simultaneously increased, diminishing the contribution of the Reynolds stress drive to the total poloidal momentum balance relative to the viscous terms No bicoherence above the noise level was observed in any of the discharges studied here Overview Viscosity calculations Using a cylindrical approximation, the poloidal momentum evolution equation is given by: [3] at steady state before a bias is applied, Reynolds stress term is balanced by poloidal viscosity ( μ θ ) and neutral damping ( ν in ) A polynomial fit is applied to the shot-by-shot Reynolds stress profile, shown in green on the right, and the appropriate spatial derivative is taken to determine the approximate flow drive This flow drive is divided by the total damping ( μ θ +ν in ) to get an estimate of the expected poloidal flow due to the RS if it were constant everywhere on the flux surface A fit of the shot-by-shot V f profile is used to estimate the local E r profile, plotted below in black T e gradient in this region is unknown, but will lead to small changes in E r The regions where there is significant deviation of the measured E r from the value predicted neoclassically from PENTA correspond to the regions of high measured Reynolds stress flow drive Summary Reynolds stress flow drive measured with the probe is large compared to the calculated neoclassical poloidal viscosity and measured E r profile Radial regions of large flow drive correspond to regions where the measured E r deviates significantly from neoclassical predictions Future work will investigate the relationship between the Reynolds stress flow drive, edge radial electric field, and parallel flows Reduce levels of biasing to re-introduce low frequency zonal flow signatures and measure the corresponding Reynolds stress PENTA Neoclassical E r Predictions ErEr ErEr EθEθ EθEθ V || I sat VfVf VfVf VfVf VfVf VfVf VfVf B B No bicoherence was detected above the noise level on any fluctuating signals during this set of experiments, including when a bias was applied When a large bias is applied, E r shear may reduce turbulence to a level too low to drive zonal flows External torque applied by the bias probe becomes the dominant forcing term in the momentum balance equation rather than Reynolds stress Reynolds stress probe Probe is located at the outboard midplane of the device, in a region of both low |B| on a magnetic flux surface and “bad” curvature, where fluctuations are expected to be largest Flux surfaces are most compressed where probe is scanned, so that the radial derivative of the Reynolds stress may be larger here than at other poloidal locations Flow drive calculated here will almost certainly be higher than the flux surface average Neoclassical poloidal viscosity ( μ θ ) is calculated approximately by using the purely poloidal term of the expression for an arbitrary stellarator configuration [4] Same experimental profiles used here as for neoclassical E r predictions Neutral density profile from DEGAS neutral gas code Neutral damping is small compared to neoclassical term, but not negligible at the edge where probe measurements are taken The Reynolds stress flow drive is measured where fluctuations and spatial gradients of fluctuations should be highest Local RS flow drive measurements are scaled down to compare to characteristics of the measured perpendicular flow profile Proper flux surface average of the Reynolds stress profile is impractical to measure in complex geometry Probability density functions of the fluctuating portions of v r and v θ demonstrate how anisotropy changes with minor radius Biased discharges PDF of velocity fluctuations PENTA code [2] calculates the neoclassical particle fluxes for a set of plasma parameters in a given magnetic configuration, then finds the ambipolar radial electric field These calculations do not account for ECRH driven flux, but this is expected to be small towards the edge “Ion root” solution exists at all positions across the minor radius, so “electron root” solutions in the core are not plotted here Ion temperature from CHERS measurements in a methane discharge T i input into calculations is scaled down to account for removal of C ion species from plasma