56th Annual Meeting of the Division of Plasma Physics, October 27 – October 31, 2014, New Orleans, LA Increase ion temperature with neutral beams: Study.

Slides:



Advertisements
Similar presentations
Ion Heating and Velocity Fluctuation Measurements in MST Sanjay Gangadhara, Darren Craig, David Ennis, Gennady Fiskel and the MST team University of Wisconsin-Madison.
Advertisements

I. Opening I-1. Welcome address U.Stroth I-2. Logistics M.Ramisch I-3. Opening remarks H.Yamada II. Definition of the goal of CWGM5 II-1. Brief review.
SUGGESTED DIII-D RESEARCH FOCUS ON PEDESTAL/BOUNDARY PHYSICS Bill Stacey Georgia Tech Presented at DIII-D Planning Meeting
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.
Steps Toward a Compact Stellarator Reactor Hutch Neilson Princeton Plasma Physics Laboratory ARIES Team Meeting October 3, 2002.
GTC Status: Physics Capabilities & Recent Applications Y. Xiao for GTC team UC Irvine.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
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.
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.
Advanced Tokamak Plasmas and the Fusion Ignition Research Experiment Charles Kessel Princeton Plasma Physics Laboratory Spring APS, Philadelphia, 4/5/2003.
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,
The toroidal current is consistent with numerical estimates of bootstrap current The measured magnetic diagnostic signals match predictions of V3FIT Comparisons.
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.
Plasma-wall interactions during high density operation in LHD
N OVIMIR A. P ABLANT M. B ITTER, L.F. D ELGADO -A PARICIO, M. G OTO, K.W. H ILL, S. L AZERSON, S. M ORITA, L. R OQUEMORE N OVIMIR A. P ABLANT M. B ITTER,
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.
Compact Stellarator Approach to DEMO J.F. Lyon for the US stellarator community FESAC Subcommittee Aug. 7, 2007.
(I) Microturbulence in magnetic fusion devices – New insights from gyrokinetic simulation & theory F. Jenko, C. Angioni, T. Dannert, F. Merz, A.G. Peeters,
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.
QAS Design of the DEMO Reactor
MCZ MCZ NCSX Mission Acquire the physics data needed to assess the attractiveness of compact stellarators; advance understanding.
SMK – APS ‘06 1 NSTX Addresses Transport & Turbulence Issues Critical to Both Basic Toroidal Confinement and Future Devices NSTX offers a novel view into.
18th International Spherical Torus Workshop, Princeton, November 2015 Magnetic Configurations  Three comparative configurations:  Standard Divertor (+QF)
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,
52 nd APS-DPP Annual Meeting, November, 8-12, 2010, Chicago, IL Plasma Pressure / BJ Contours Poloidal dimension Radial dimension Toroidal Angle (rad)
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,
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.
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 , 2010, Salt Lake City, Utah 5-pin Langmuir probe configured to measure the Reynolds.
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
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.
4. Neoclassical vs Anomalous Transport: Crucial Issue for Quasisymmetric Stellarators Overview of HSX Experimental Program J.N. Talmadge, A. Abdou, A.F.
53rd Annual Meeting of the Division of Plasma Physics, November 13 – November 18, 2011, Salt Lake City, UT Laser Blow-Off Impurity Injection Experiments.
= 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.
52nd Annual Meeting of the Division of Plasma Physics, November 8 – November 12, 2010, Chicago, IL Development of Laser Blow-Off Impurity Injection Experiments.
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.
Bootstrap current in quasi-symmetric stellarators Andrew Ware University of Montana Collaborators: D. A. Spong, L. A. Berry, S. P. Hirshman, J. F. Lyon,
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.
54th Annual Meeting of the APS Division of Plasma Physics, October 29 – November 2, 2012, Providence, Rhode Island 3-D Plasma Equilibrium Reconstruction.
18 th Int’l Stellarator/Heliotron Workshop, 29 Jan. – 3 Feb. 2012, Canberra – Murramarang Reserve, Australia Recent Results and New Directions of the HSX.
Hard X-rays from Superthermal Electrons in the HSX Stellarator Preliminary Examination for Ali E. Abdou Student at the Department of Engineering Physics.
57 th Annual Meeting of the Division of Plasma Physics. November 16-20, Savannah, GA 1.Stangeby, P. C. The plasma boundary of magnetic fusion devices.
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
Modeling Neutral Hydrogen in the HSX Stellarator
0.5 T and 1.0 T ECH Plasmas in HSX
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik1, D.L. Brower2, C. Deng2,
Magnetic fluctuation measurements in HSX and its impact on transport
15TH WORKSHOP ON MHD STABILITY CONTROL
Impurity Transport Research at the HSX Stellarator
Characteristics of Biased Electrode Discharges in HSX
Targeted Physics Optimization in HSX
First Experiments Testing the Working Hypothesis in HSX:
Targeted Physics Optimization in HSX
T. Morisaki1,3 and the LHD Experiment Group
T. Morisaki1,3 and the LHD Experiment Group
Stellarator Program Update: Status of NCSX & QPS
Presentation transcript:

56th Annual Meeting of the Division of Plasma Physics, October 27 – October 31, 2014, New Orleans, LA Increase ion temperature with neutral beams: Study role of high-effective transform (i eff ~ 3) on ion confinement with tangential injection into high-electron temperature plasma Explore transport with E r in reactor-relevant ion root Study low-collisionality ion transport Higher density operation with neutral source control: Higher density core plasma and interface to scrape-off layer Study impurity transport and exhaust in ion root E r Reduce neutral source in core to facilitate density and exhaust control Explore feasibility of optimizing for reducing turbulent transport Builds on quasisymmetric magnetic topology which is optimized for improved neoclassical transport Upgrades needed for physics program: New vacuum vessel and type #1 coils for NBI and diagnostic access, improved conditioning, larger plasma/wall separation, more room for flexible divertor configurations ECH: 500 kW, 0.3 s, 56 GHz; energetic electron transport and beam target NBI: 2 X 300 kW 40 keV 0.3s systems (Budker Inst./ Compass D units) Infrastructure upgrades to accommodate new capabilities Bader UP , Talmadge (UP ) HSX Upgrade Overview of the HSX Program and Plans for Upgrade D.T. Anderson & the HSX Team HSX Plasma Laboratory, Univ. of Wisconsin, Madison, USA; Overview Present experimental program concentrated on 4 main areas: 1) equilibrium reconstruction, 2) core transport, 3) plasma flows and electric fields and 4) edge transport. Experimental and theoretical results illuminate physics issues that impact Wendelstein 7-X, which comes on-line in  Equilibrium reconstruction demonstrates time evolution of bootstrap current, critical to proper functioning of W7-X divertor.  Heat pulse propagation experiment demonstrates lack of stiffness in heat transport, in agreement with 3-D gyrokinetic calculations using two kinetic species  Improvement in neoclassical theory are being benchmarked and demonstrated experimentally.  Work has begun on using motional stark effect to measure radial electric field and bootstrap current profile in HSX.  Edge studies show electric field in edge island which could impact W7-X divertor and is not included in EMC3-EIRENE modeling. Proposal submitted by Prof. O. Schmitz as PI investigates 3-D equilibrium reconstruction and impact on edge transport and island divertor performance in W7-X involving HSX, CTH (Auburn) and small plasma device. HSX upgrade planned to focus on hotter ion temperatures, ion root transport, turbulent transport mitigation and divertor optimization. Equilibrium Reconstruction Core Transport Plasma Flow & Electric Fields Edge Transport Equilibrium Reconstruction Theory and Modeling Optimized coil placement Spark V3FIT Experiment Reduced profile uncertainty Eddy current modeling Bootstrap current evolution & rational surfaces eChlechowitz UP Core Transport Theory and Modeling GENE calculations confirm experimental lack of stiffness in core. Faber CP (Monday) Optimization of auxiliary coil currents to reduce TEM transport Talmadge UP Experiment Pulse propagation experiments indicate transport is not stiff in core. Weir TI (Monday) Interferometer measurements of density fluctuations show increase with decreasing L n (off-axis heating), consistent with TEM drive Deng UP Plasma Flow & Electric Fields Theory and Modeling Compare DKES and PENTA codes, both assume mono- energetic distribution, to SFINCS (Landreman) and FORTEC-3D (Satake) which do not Smoniewski UP Experiment Inboard/outboard CXRS measurement of Pfirsch-Schluter flow indicates larger core Er than measured previously Kumar UP Examine Motional Stark Effect to measure Er and B using spectral fitting Ruiz UP and polarimetry Dobbins UP Reynolds stress measurements at plasma edge suggest that in a quasisymmetric stellarator, it influences Er Wilcox YP (Friday) Edge Transport Theory and Modeling Simulate edge Te, ne and plasma flow at edge with EMC3-EIRENE given different boundary conditions Bader UP Compare DEGAS neutral calculations to EIRENE Stephey Experiment Electric fields measured within islands that is not modeled with EMC3-EIRENE Akerson UP Study neutral fueling in preparation for pumped limiter studies Stephey UP Proposed Collaboration with W7X Joint proposal with Auburn University aims at investigating 3-D equilibrium effects on edge transport and divertor performance at Wendelstein 7-X. P.I.: O. Schmitz, UW-Madison Domestic activities include HSX, CTH, helicon linear device, EMC3- EIRENE and V3FIT. Briesemeister 2013: CXRS measurements of E r do not agree with model at center and edge. Is the model or the expt in error? Schmitt, PoP Sept. 2014: momentum conservation and E r impacts bootstrap current in HSX Activities on HSX center on validation and testing of EMC3- EIRENE, implement and test line ratio spectroscopy on helium as a divertor diagnostic, and explore helium exhaust. Proposal takes advantage of HSX strength in examining core- edge coupling.