Comparison of Plasma Flows and Currents in HSX to Neoclassical Theory


 Bryce Bishop
 1 years ago
 Views:
Transcription
1 1 EX/P330 Comparison of Plasma Flows and Currents in HSX to Neoclassical Theory D.T. Anderson 1, A.R. Briesemeister 1, J.C. Schmitt 2, F.S.B. Anderson 1, K.M. Likin 1, J.N. Talmadge 1, G.M. Weir 1, K. Zhai 1 1 University of Wisconsin, Madison, WI, USA 2 Princeton Plasma Physics Laboratory, Princeton, NJ, USA contact of main author: Abstract. The Helically Symmetric Experiment (HSX) was designed to have an axis of symmetry in the helical direction, reduced neoclassical transport and small equilibrium currents due to the high effective transform. Unlike other stellarators in which B varies in all directions on a flux surface, plasmas in HSX are free to rotate in the direction of quasihelical symmetry. In this paper we will present measurements with Charge Exchange Recombination Spectroscopy (CXRS) that demonstrate that intrinsic plasma flows are predominantly in the direction of symmetry. Whereas previous neoclassical calculations did not conserve momentum, we show that the experimental results agree better with recent modifications to neoclassical theory that do conserve momentum. Also, we present a 3D equilibrium reconstruction of the plasma pressure and current profile utilizing a set of magnetic diagnostics and demonstrate that these results are in reasonable agreement with expectations from the same neoclassical model. 1. Introduction Measuring and modeling the radial electric field and plasma flow is important for understanding plasma transport and stability. Sheared flows driven by steep radial electric field profiles have been linked to reduced turbulent transport in both Hmode plasmas and plasmas with internal transport barriers [1]. The radial electric field can also reduce neoclassical particle transport, which is especially important in stellarators and other devices with significant nonsymmetric magnetic field components. Nonaxisymmetric fields exist in tokamaks because of the finite coil effects and have been intentionally introduced primarily for ELM suppression. Nonresonant magnetic perturbations in the DIIID tokamak have been shown to cause a nonzero flow offset that can cause the plasma to spin without momentum injection from neutral beams [2]. A common method to calculate the flows and electric field in stellarators is to use the DKES [3] (Drift Kinetic Equation Solver) code. DKES uses the incompressible flow E B E B approximation:, where denotes flux surface average. This 2 2 B B approximation eliminates the changes in kinetic energy which would occur as a result of radial drift in the presence of E r, making the drift kinetic equation monoenergetic and allowing the use of a collision operator that only includes pitch angle scattering. This form of the drift kinetic equation has a nonphysical singularity at the resonant value of the radial electric field: E m n ι m res r vtabθ [4], where θ B is the poloidal magnetic field, vta is the
2 2 EX/P330 thermal velocity for species a, n and m are respectively the toroidal and poloidal mode numbers of the dominant component(s) of the magnetic field spectrum. For HSX, the dominant helical mode has n=4 and m=1. It has been shown that near a resonance in the radial electric field DKES does not correctly calculate the particle diffusion coefficient [4]. This paper will focus on the outer half of the HSX plasma where E r is predicted to be much smaller than the resonant value for the hydrogen ions. The pitch angle scattering collision operator does not conserve momentum. Three techniques [5,6,7] developed to correct the monoenergetic transport coefficients calculated by DKES to account for momentum exchange have been implemented in the current version of the PENTA [8] code. All three techniques use the diffusion coefficients calculated by DKES, and are therefore not accurate near resonant values of E r. The SugamaNishimura method was used for the calculations including momentum conservation shown in this paper. Figure 1 The electron temperature and density profiles were measured using Thomson scattering and used for the PENTA and DKES calculations. The C +6 temperature and density were measured using the CHERS system. n H+ is found by subtracting the C +6 charge density from n e. 2. CXRS Measurements and Plasma Flow The plasma in HSX for these studies and the reconstruction efforts detailed in the next section are created and heated by up to 100 kw of 1 st harmonic Omode ECRH with a 28 GHz gyrotron at a magnetic field strength of B=1.0 T. The launch angle is perpendicular to the magnetic axis, introducing negligible toroidal current drive. Electron temperature and density profiles are measured by a 10 channel Thomson scattering system. Electron temperatures up to nearly 3 kev are measured in the core. With a central density ~ 4 x m 3, ECE measurements show a minimal suprathermal component to the plasma, and good agreement is seen in stored energy between integrated profiles and diamagnetic measurements. Doppler spectroscopy indicates that, by comparison with the electrons, the ions are cold with temperatures in the range of ev. The CXRS system is used to measure the velocity, temperature, and density of C +6 ions in HSX. A 30 kev, 4 Amp, 3 ms diagnostic neutral beam [9] is fired vertically through the plasma. The neutral beam does not cause any measurable perturbations to the electron temperature and density profiles. The Doppler shift, broadening and strength of the 529 nm emission line from C +5 ions is measured using two 0.75 m CzernyTurner spectrometers. Electron multiplying ccd s capture a series of images of the spectra during each discharge. Each image is integrated for 5 ms and read out in 1 ms. Images captured before and after the beam is fired are used to remove the background light. The spectral position of the emission line is measured during a series of shots with the magnetic field in the counter clockwise direction and compared to the position measured with the field in the clockwise direction. All components of the flow velocity should reverse when the field is reversed. Using the difference in the measured emission line position between the two cases effectively doubles the Doppler shift caused by the plasma velocity. This technique also eliminates systematic measurement error caused by the uncertainty in the relative strengths of the fine structure
3 3 EX/P330 components of the emission line. A spectral calibration is performed every shot using a neon calibration lamp to account for instrumental drift throughout the day. The CXRS system measures C +6 density. Coronal equilibrium calculations and passive spectroscopic measurements indicate that significant populations of lower ionizations states of carbon are present, especially in the outer half of the plasma. Since no quantitative measurement of the density of the other ion species exists, an upper bound on the H + density is set by the difference between the electron density and the C +6 charge density, and used as an input for the neoclassical calculations. The flow velocity is measured at ten radial locations from two different directions as shown on the diagram in Figure 2. One direction is a measurement of the flow in an approximately poloidal direction while the other is in an approximately toroidal direction. The views are not orthogonal. The two measurements provide constraints on the local flow velocity. A third constraint on the flow velocity vector is provided by the assumption that there will be no net flow in the Ψ direction. The velocity measured by Figure 2 Drawing of the HSX CHERS system showing the neutral beam along with the viewing chords, the flux surfaces and a portion of the vacuum vessel each view, shown in Figure 3(a), is a beam density weighted average of the local flow velocity along the viewing direction throughout each beam/view intersection volume. These measurements can be used to determine the flows parallel and perpendicular to the direction of symmetry within a magnetic surface. Outside of r/a = 0.4, the errors due to the large beam width compared to the magnetic surface size are small. Figure 3(b) shows that the measured flows are predominantly in the direction of symmetry as one would expect (equivalent to the toroidal direction in a tokamak), with only small flow velocities in the perpendicular direction within the magnetic surface. Fig. 3 (a) Measured flow velocity in the toroidal view (green) and the poloidal view (purple); (b) Projection of flow velocity in the quasihelically symmetric direction and its normal.
4 4 EX/P330 The radial electric field, along with the pressure gradient, drive flow perpendicular to the magnetic field direction. A flow parallel to the magnetic field can arise as a result of the plasma viscosity. HSX was optimized for quasihelical symmetry. This helical direction of quasisymmetry reduces flow damping along the helical direction [10], allowing significant parallel flows to arise. Parallel flows have been calculated both with the DKES code and with the PENTA code using the momentum conservation correction techniques. Momentum conservation has little effect on the particle fluxes and the ambipolar electric field, but a large effect is observed on the parallel flow as shown in Figure 4. The PENTA calculation is in reasonable agreement with the Fig. 4 Measured parallel flow and neoclassical calculation with (red) and without (blue) momentum conservation. measurements over a large portion of the plasma, while DKES predicts virtually no parallel flow. 3. Equilibrium Currents In the absence of an induced ohmic current or current drive, the parallel current consists of the PfirschSchlüter current (which integrates to zero on a flux surface) and the bootstrap current. The bootstrap current can be significant at higher beta values and can modify the rotational transform and the magnetic configuration. Accurately modeling this current is crucial in predicting performance in optimized stellarator devices. We have seen above that including momentum conservation in modeling quasisymmetric devices leads to considerably different results in the parallel flow compared to previous models, and in much better agreement with measurements. It could be expected that momentum conservation might have a large effect on the bootstrap current as well. Calculations with PENTA do show a strong dependence of the bootstrap current on the radial electric field. Experiments have been performed to examine the equilibrium currents in HSX. For the studies reported we have utilized a set of magnetic flux loops to measure signals external to the plasma and used reconstruction techniques (V3FIT [11]) to infer the current and pressure profiles which give good agreement with the magnetic diagnostic signals. The reproducibility of HSX discharges and low MHD activity provide reasonable signals for this analysis. Analysis of these signals has been used to demonstrate that the PfirschSchluter current in HSX rotates helically in going around the torus and has a magnitude reduced by a factor of (Nm ) (3 for HSX) from an equivalent tokamak. These results were reported at the IAEA in 2008 [12]. This factor algebraically goes through all of neoclassical transport for quasihelical symmetry. Early in the discharge, the magnetic signals are dominated by the PfirschSchluter currents which are set up rapidly on the equilibrium timescale. The unidirectional bootstrap current then evolves over a timescale longer than the discharge time in HSX.
5 Amps 5 EX/P330 The total toroidal current in HSX is measured by a Rogowski coil encircling the plasma. Discharges were analyzed with both 100 kw and 50 kw ECH heating power, but only the kw ECH sec Figure 5 Total toroidal current measured by the Rogowski coil for B T clockwise (red) and counterclockwise kw are reported here. The current evolution is even slower at 100 kw due to the increased electron temperature. Figure 5 shows the time evolution of the total current as measured by the Rogowski coil. To be sure that we were not driving current in a particular direction due to misalignment of the ECH launching structure, the field direction was reversed. The solid red curve is the current in this case (the dashed red curve has the sign reversed for comparison). This clearly shows no significant current driven in a specific direction through some external momentum input, and also illustrates the reproducibility of the discharges. Figure 6(a) shows the profiles measured by the Thomson scattering and CXRS system used for analysis by PENTA, while 6(b) shows the electric field as calculated by PENTA. Near the core where we have a steep gradient in T e we can have either ion or electron root solutions. The bootstrap current density depends critically on the sign of the electric field in the multiple root region as shown in Figure 6(c). (a) (b) (c) Figure 6 Penta input profiles, electric field, and bootstrap current density predictions While the profiles and stored energy are stationary, the bootstrap current continues to evolve in time during the discharge. Fitting this evolution to an exponential L/R rise gives a steadystate value of ~380A with a rise time of ~50 ms. As seen in Figure 6(c), the bootstrap current in the core actually changes sign based on whether the plasma is in the electron or ion root in this region. If the core plasma is assumed to be in the electron root, then the integrated current is <10 A. If the ion root solution is assumed, the integrated current is of the order 260A, much closer to the experimental value. A 1D diffusion equation for the rotational transform by Strand and Houlberg [13] is used to model the current evolution on the way to the steadystate conditions. This is the profile that is then used as input into the equilibrium reconstruction for analysis of the measured flux loop signals.
6 6 EX/P330 To perform the reconstruction, an initial guess of the pressure and current profile is made. The initial pressure profile corresponds to the experimental measurements of the density and temperature. The initial current profile estimate has just been described. The reconstruction is performed by the V3FIT code which minimizes the mismatch between the measured signals and a model pressure and current profile. There are a total of 5 plasma parameters to be optimized: two free parameters for the pressure profile, two for the current profile and one for the net toroidal flux within the last closed flux surface. Figure 7 shows how the initial pressure profile (shown in blue) based on the experimental data gives a good fit to the poloidal magnetic field measured by a Bdot coil array internal to the vacuum chamber. The black dashed line is the local signal predicted by V3FIT based solely on the PfirschSchluter component of the current. The DC offset and slight variations seen in the blue trace are the modification of Figure 7 Predicted and measured flux loop signals from the PfirschSchluter and bootstrap currents (blue) and improved agreement with V3FIT reconstruction. those signals introduced by the modeled bootstrap current, With the reconstruction (red trace), the χ 2 value is reduced by 1/3, providing an even better fit to the coil data and slightly modifying the pressure profile as shown in Figure 8. Pa Good agreement of the reconstructed current profile with the calculated profile has also been observed, however a wide range of profiles also show reasonable agreement with the data, indicating that the measured edge magnetic signals are not that sensitive to the small bootstrap current, especially given its localization to the core / LCFS Figure 8 Initial pressure profile (blue) and reconstructed profile by V3FIT (red) 4. Summary A direction of symmetry in quasihelically symmetric stellarators offers the possibility for large flows with positive impacts on confinement as in the tokamak. Large flows in the direction of quasisymmetry have been observed in HSX without any external momentum input. Agreement between the level of the parallel flow between calculations and experiment are only achieved if momentum conservation is included in the model through use of the PENTA code. Using the PENTA formulation allows calculations to be performed with a single code spanning cases from pure axisymmetry, to rippled/perturbed tokamaks, to quasisymmetric configurations, to full 3D systems.
7 7 EX/P330 Understanding the bootstrap current and its evolution is critical for future devices where the current will evolve over minutes or more. The current can have significant impact on the configuration and device performance. The bootstrap and PfirschSchluter currents in HSX have been estimated from external flux loops signals modelled with PENTA and the V3FIT codes. An evolution equation has been applied to estimate the bootstrap current profile during its approach to steadystate. V3FIT has been used in a forward direction to predict signals from the modelled currents and in a reconstruction mode to achieve better agreement between the measured and predicted signals with slight profile adjustments. Results also point to the need for additional constraints and data (in addition to the present external flux loops) to definitively determine the current profile with high confidence. The results confirm the unique helical nature of the PfirschSchluter current in HSX and the reduction in magnitudes of both currents by the predicted factor of three due to the quasihelical symmetry. References [1] Fujisawa A. Experimental studies of structural bifurcation in stellarator plasmas. Plasma Physics and Controlled Fusion. 2003;45(8):R1 R88. [2] Garofalo AM, Burrell KH, DeBoo JC, degrassie JS, Jackson GL, Lanctot M, et al. Observation of Plasma Rotation Driven by Static Nonaxisymmetric Magnetic Fields in a Tokamak. Phys. Rev. Lett Nov 7;101(19): [3] Hirshman SP, Shaing KC, van Rij WI, Beasley CO, Crume EC. Plasma transport coefficients for nonsymmetric toroidal confinement systems. Phys. Fluids. 1986;29(9):2951. [4] Beidler CD, Isaev MY, Kasilov SV, Kernbichler W, Maassberg H, Murakami S, et al. ICNTSImpact of Incompressible ExB Flow in Estimating MonoEnergetic Transport Coefficients. 2007; [5] Sugama H, Nishimura S. How to calculate the neoclassical viscosity, diffusion, and current coefficients in general toroidal plasmas. Physics of Plasmas. 2002;9:4637. [6] Maaßberg H, Beidler CD, Turkin Y. Momentum correction techniques for neoclassical transport in stellarators. Phys. Plasmas. 2009;16(7): [7] Taguchi M. A method for calculating neoclassical transport coefficients with momentum conserving collision operator. Phys. Fluids B. 1992;4(11):3638. [8] Spong DA. Generation and damping of neoclassical plasma flows in stellarators. Phys. Plasmas May;12(5): [9] Abdrashitov GF, Davydenko VI, Deichuli PP, Den Hartog DJ, Fiksel G, Ivanov AA, et al. A diagnostic neutral beam system for the MST reversedfield pinch. Papers from the thirteenth topical conference on high temperature plasma diagnostics [Internet]. Tuscon, Arizona (USA): AIP; 2001 [cited 2010 Jan 12]. p Available from: [10] Gerhardt SP, Talmadge JN, Canik JM, Anderson DT. Measurements and modeling of plasma flow damping in the Helically Symmetric experiment. Phys. Plasmas May;12(5): [11] Hanson, J.D., Hirshman, S.P., Knowlton, S.F., Lao, L.L., Lazarus, E.A., and Shields, J.M., V3FIT: a code for threedimensional equilibrium reconstruction, Nucl. Fusion 49 (2009) [12] J.N. Talmadge et al., 22 nd IAEA Fusion Energy Conference, Geneva, Switzerland, paper EX/25 (2008). [13] P.I. Strand and W.A. Houlberg, Phys. Plasmas 8, 2782 (2001).
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX
1 Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1), D.L. Brower 2), C. Deng 2), D.T. Anderson 1), F.S.B. Anderson 1), A.F.
More informationReduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX
Reduction of Neoclassical Transport and Observation of a Fast Electron Driven Instability with Quasisymmetry in HSX J.M. Canik 1, D.L. Brower 2, C. Deng 2, D.T.Anderson 1, F.S.B. Anderson 1, A.F. Almagri
More informationShear Flow Generation in Stellarators  Configurational Variations
Shear Flow Generation in Stellarators  Configurational Variations D. A. Spong 1), A. S. Ware 2), S. P. Hirshman 1), J. H. Harris 1), L. A. Berry 1) 1) Oak Ridge National Laboratory, Oak Ridge, Tennessee
More informationNumerical calculation of the Hamada basis vectors for threedimensional toroidal magnetic configurations
PHYSICS OF PLASMAS 12, 072513 2005 Numerical calculation of the Hamada basis vectors for threedimensional toroidal magnetic configurations J. N. Talmadge and S. P. Gerhardt a HSX Plasma Laboratory, University
More informationInitial Experimental Program Plan for HSX
Initial Experimental Program Plan for HSX D.T. Anderson, A F. Almagri, F.S.B. Anderson, J. Chen, S. Gerhardt, V. Sakaguchi, J. Shafii and J.N. Talmadge, UWMadison HSX Plasma Laboratory Team The Helically
More informationFirst Experiments Testing the Working Hypothesis in HSX:
First Experiments Testing the Working Hypothesis in HSX: Does minimizing neoclassical transport also reduce anomalous transport? J. N. Talmadge HSX Plasma Laboratory University of WisconsinMadison Special
More informationInnovative Concepts Workshop Austin, Texas February 1315, 2006
Don Spong Oak Ridge National Laboratory Acknowledgements: Jeff Harris, Hideo Sugama, Shin Nishimura, Andrew Ware, Steve Hirshman, Wayne Houlberg, Jim Lyon Innovative Concepts Workshop Austin, Texas February
More informationResistive Wall Mode Control in DIIID
Resistive Wall Mode Control in DIIID by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil
More informationExperimental test of the neoclassical theory of poloidal rotation
Experimental test of the neoclassical theory of poloidal rotation Presented by Wayne Solomon with contributions from K.H. Burrell, R. Andre, L.R. Baylor, R. Budny, P. Gohil, R.J. Groebner, C.T. Holcomb,
More informationDirect drive by cyclotron heating can explain spontaneous rotation in tokamaks
Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.J. Zheng Institute for Fusion Studies University of Texas at Austin 12th USEU Transport Task Force Annual
More informationSpontaneous tokamak rotation: observations turbulent momentum transport has to explain
Spontaneous tokamak rotation: observations turbulent momentum transport has to explain Ian H Hutchinson Plasma Science and Fusion Center and Nuclear Science and Engineering Massachusetts Institute of Technology
More informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationEffects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal
Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.
More informationImpurity expulsion in an RFP plasma and the role of temperature screening
Impurity expulsion in an RFP plasma and the role of temperature screening S. T. A. Kumar, D. J. Den Hartog, R. M. Magee, G. Fiksel, D. Craig Department of Physics, University of WisconsinMadison, Madison,Wisconsin,
More informationPhysics and Operations Plan for LDX
Physics and Operations Plan for LDX Columbia University A. Hansen D.T. Garnier, M.E. Mauel, T. Sunn Pedersen, E. Ortiz Columbia University J. Kesner, C.M. Jones, I. Karim, P. Michael, J. Minervini, A.
More informationControl of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal
Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A. Roberds,
More informationRecent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science
Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant
More informationObservation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H and QHmode Plasmas
Observation of Reduced Core Electron Temperature Fluctuations and Intermediate Wavenumber Density Fluctuations in H and QHmode Plasmas EX/P535 L. Schmitz 1), A.E. White 1), G. Wang 1), J.C. DeBoo 2),
More informationOscillatingField CurrentDrive Experiment on MST
OscillatingField CurrentDrive Experiment on MST K. J. McCollam, J. K. Anderson, D. J. Den Hartog, F. Ebrahimi, J. A. Reusch, J. S. Sarff, H. D. Stephens, D. R. Stone University of WisconsinMadison D.
More informationGA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIIID by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J.
GA A27822 THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIIID by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J. GROEBNER JUNE 2014 DISCLAIMER This report was prepared as an account of work
More information(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft Xray. T_e contours (ECE) r (minor radius) time time
Studies of Spherical Tori, Stellarators and Anisotropic Pressure with M3D 1 L.E. Sugiyama 1), W. Park 2), H.R. Strauss 3), S.R. Hudson 2), D. Stutman 4), XZ. Tang 2) 1) Massachusetts Institute of Technology,
More informationStudy of B +1, B +4 and B +5 impurity poloidal rotation in Alcator CMod plasmas for 0.75 ρ 1.0.
Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator CMod plasmas for 0.75 ρ 1.0. Igor Bespamyatnov, William Rowan, Ronald Bravenec, and Kenneth Gentle The University of Texas at Austin,
More informationRFP helical equilibria reconstruction with V3FITVMEC
RFP helical equilibria reconstruction with V3FITVMEC D. Terranova 1 J.D. Hanson 2, S.P. Hirshman 3, L. Marrelli 1 1 Consorzio RFX, Associazione EURATOMENEA sulla Fusione, Padova, Italy 2 Auburn University,
More informationMeasurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device
REVIEW OF SCIENTIFIC INSTRUMENTS 76, 053505 2005 Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device K. Ida, a
More informationInfluence of ECR Heating on NBIdriven Alfvén Eigenmodes in the TJII Stellarator
EX/P Influence of ECR Heating on NBIdriven Alfvén Eigenmodes in the TJII Stellarator Á. Cappa, F. Castejón, T. Estrada, J.M. Fontdecaba, M. Liniers and E. Ascasíbar Laboratorio Nacional de Fusión CIEMAT,
More informationIssues of Perpendicular Conductivity and Electric Fields in Fusion Devices
Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices Michael Tendler, Alfven Laboratory, Royal Institute of Technology, Stockholm, Sweden Plasma Turbulence Turbulence can be regarded
More informationStellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK
Stellarators Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 6 th February 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously... Toroidal devices
More informationFiniteOrbitWidth Effect and the Radial Electric Field in Neoclassical Transport Phenomena
1 TH/P218 FiniteOrbitWidth Effect and the Radial Electric Field in Neoclassical Transport Phenomena S. Satake 1), M. Okamoto 1), N. Nakajima 1), H. Sugama 1), M. Yokoyama 1), and C. D. Beidler 2) 1)
More informationObservations of CounterCurrent Toroidal Rotation in Alcator CMod LHCD Plasmas
1 EX/P54 Observations of CounterCurrent Toroidal Rotation in Alcator CMod LHCD Plasmas J.E. Rice 1), A.C. InceCushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke
More informationGA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES
GA A311 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES by C.C. PETTY, M.R. WADE, J.E. KINSEY, R.J. GROEBNER, T.C. LUCE, and G.M. STAEBLER AUGUST 1999 This report
More informationOn the physics of shear flows in 3D geometry
On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOMCIEMAT, Madrid, Spain Recent experiments have shown the importance of multiscale (longrange)
More informationNonSolenoidal Plasma Startup in
NonSolenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APSDPP, Nov. 2, 28 1 PointSource DC Helicity Injection Provides Viable NonSolenoidal Startup Technique
More informationFormation of Highb ECH Plasma and Inward Particle Diffusion in RT1
J Fusion Energ (2010) 29:553 557 DOI 10.1007/s1089401093276 ORIGINAL RESEARCH Formation of Highb ECH Plasma and Inward Particle Diffusion in RT1 H. Saitoh Z. Yoshida J. Morikawa Y. Yano T. Mizushima
More informationObservation of NeoClassical Ion Pinch in the Electric Tokamak*
1 EX/P629 Observation of NeoClassical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.L. Gauvreau, P.A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,
More informationComparison of Deuterium Toroidal and Poloidal Rotation to Neoclassical Theory in the DIIID Tokamak
1 EX/P319 omparison of Deuterium Toroidal and Poloidal Rotation to Neoclassical Theory in the DIIID Tokamak B.A. Grierson 1, K.H. Burrell and W.M. Solomon 1 1 Princeton Plasma Physics Laboratory, Princeton
More informationW.A. HOULBERG Oak Ridge National Lab., Oak Ridge, TN USA. M.C. ZARNSTORFF Princeton Plasma Plasma Physics Lab., Princeton, NJ USA
INTRINSICALLY STEADY STATE TOKAMAKS K.C. SHAING, A.Y. AYDEMIR, R.D. HAZELTINE Institute for Fusion Studies, The University of Texas at Austin, Austin TX 78712 USA W.A. HOULBERG Oak Ridge National Lab.,
More informationDer Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk
MaxPlanckInstitut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator
More informationIon Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device
Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),
More informationRotation Speed Differences of Impurity Species in the DIIID Tokamak and Comparison with Neoclassical Theory
Rotation Speed Differences of Impurity Species in the DIIID Tokamak and Comparison with Neoclassical Theory L.R. Baylor, K.H. Burrell*, R.J. Groebner*, D.R. Ernst #, W.A. Houlberg, M. Murakami, and The
More informationDriftDriven and TransportDriven Plasma Flow Components in the Alcator CMod Boundary Layer
DriftDriven and TransportDriven Plasma Flow Components in the Alcator CMod Boundary Layer N. Smick, B. LaBombard MIT Plasma Science and Fusion Center PSI19 San Diego, CA May 25, 2010 Boundary flows
More informationPredictive Study on High Performance Modes of Operation in HL2A 1
1 EX/P0 Predictive Study on High Performance Modes of Oration in HLA 1 Qingdi GAO 1), R. V. BUDNY ), Fangzhu LI 1), Jinhua ZHANG 1), Hongng QU 1) 1) Southwestern Institute of Physics, Chengdu, Sichuan,
More informationEX/C35Rb Relationship between particle and heat transport in JT60U plasmas with internal transport barrier
EX/CRb Relationship between particle and heat transport in JTU plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),
More informationNoninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE
1 EX/P618 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.
More informationEffect of Resonant and Nonresonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas
1 EX/53Ra Effect of Resonant and Nonresonant Magnetic Braking on Error Field Tolerance in High Beta Plasmas H. Reimerdes 1), A.M. Garofalo 2), E.J. Strait 2), R.J. Buttery 3), M.S. Chu 2), Y. In 4),
More informationQTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.
LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 16th IAEA Fusion Conference
More informationCharacteristics of Internal Transport Barrier in JT60U Reversed Shear Plasmas
Characteristics of Internal Transport Barrier in JT6U Reversed Shear Plasmas Y. Sakamoto, Y. Kamada, S. Ide, T. Fujita, H. Shirai, T. Takizuka, Y. Koide, T. Fukuda, T. Oikawa, T. Suzuki, K. Shinohara,
More informationGA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY
GA A27398 COMPARISON OF DEUTERIUM TOROIDAL AND POLOIDAL ROTATION TO NEOCLASSICAL THEORY by B.A. GRIERSON, K.H. BURRELL and W.M. SOLOMON OCTOBER 212 DISCLAIMER This report was prepared as an account of
More informationComparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR
1 Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR W. Choe 1,2*, K. Kim 1,2, J.W. Ahn 3, H.H. Lee 4, C.S. Kang 4, J.K. Park 5, Y. In 4, J.G. Kwak 4,
More informationReduced Electron Thermal Transport in Low Collisionality Hmode Plasmas in DIIID and the Importance of Smallscale Turbulence
1 Reduced Electron Thermal Transport in Low Collisionality Hmode Plasmas in DIIID and the Importance of Smallscale Turbulence L. Schmitz, 1 C. Holland, 2 T.L. Rhodes, 1 G. Wang, 1 L. Zeng, 1 A.E. White,
More information1 EX/C43. Increased Understanding of Neoclassical Internal Transport Barrier on CHS
EX/C3 Increased Understanding of Neoclassical Internal Transport Barrier on CHS T.Minami, A.Fujisawa, H.Iguchi, Y.Liang, K.Ida, S.Nishimura, M.Yokoyama, S.Murakami, Y.Yoshimura, M.Isobe, C.Suzuki, I.Nomura,
More informationProgress of Confinement Physics Study in Compact Helical System
1st IAEA Fusion Energy Conference Chengdu, China, 161 October, 6 IAEACN149/ EX/55Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS839 Oct. 6 1 EX/55Rb Progress
More informationRotation and Neoclassical Ripple Transport in ITER
Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics
More informationTriggering Mechanisms for Transport Barriers
Triggering Mechanisms for Transport Barriers O. Dumbrajs, J. Heikkinen 1, S. Karttunen 1, T. Kiviniemi, T. KurkiSuonio, M. Mantsinen, K. Rantamäki 1, S. Saarelma, R. Salomaa, S. Sipilä, T. Tala 1 EuratomTEKES
More informationGlobal Mode Control and Stabilization for Disruption Avoidance in Highβ NSTX Plasmas *
1 EX/P807 Global Mode Control and Stabilization for Disruption Avoidance in Highβ NSTX Plasmas * J.W. Berkery 1, S.A. Sabbagh 1, A. Balbaky 1, R.E. Bell 2, R. Betti 3, J.M. Bialek 1, A. Diallo 2, D.A.
More informationD.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin  Madison 1500 Engineering Drive Madison, WI 53706
D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin  Madison 1500 Engineering Drive Madison, WI 53706 Concept Overview Implementation on PEGASUS Results Current
More informationIMPURITY ANALYSIS AND MODELING OF DIIID RADIATIVE MANTLE DISCHARGES
IMPURITY ANALYSIS AND MODELING OF DIIID RADIATIVE MANTLE DISCHARGES J. Mandrekas, W.M. Stacey Georgia Institute of Technology M. Murakami, M.R. Wade ORNL G. L. Jackson General Atomics Presented at the
More informationLocalized Electron Cyclotron Current Drive in DIII D: Experiment and Theory
Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. LinLiu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,
More informationElectrode Biasing Experiment in the Large Helical Device
1 EXC/P807 Electrode Biasing Experiment in the Large Helical Device S. Kitajima 1), H. Takahashi 2), K. Ishii 1), J. Sato 1), T. Ambo 1), M. Kanno 1), A. Okamoto 1), M. Sasao 1), S. Inagaki 3), M. Takayama
More informationTheory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus. K. C. Shaing
Theory for Neoclassical Toroidal Plasma Viscosity in a Toroidally Symmetric Torus K. C. Shaing Plasma and Space Science Center, and ISAPS, National Cheng Kung University, Tainan, Taiwan 70101, Republic
More informationIntegrated Particle Transport Simulation of NBI Plasmas in LHD )
Integrated Particle Transport Simulation of NBI Plasmas in LHD Akira SAKAI, Sadayoshi MURAKAMI, Hiroyuki YAMAGUCHI, Arimitsu WAKASA, Atsushi FUKUYAMA, Kenichi NAGAOKA 1, Hiroyuki TAKAHASHI 1, Hirohisa
More informationFormation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )
Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 3110102, Japan 1) University
More informationCONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT
CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT G. Fiksel, 1 A.F. Almagri, 1 J.K. Anderson, 1 T.M. Biewer, 1 D.L. Brower, 2 CS. Chiang, 1 B.E. Chapman, 1 J.T. Chapman,
More informationTransport Improvement Near Low Order Rational q Surfaces in DIII D
Transport Improvement Near Low Order Rational q Surfaces in DIII D M.E. Austin 1 With K.H. Burrell 2, R.E. Waltz 2, K.W. Gentle 1, E.J. Doyle 8, P. Gohil 2, C.M. Greenfield 2, R.J. Groebner 2, W.W. Heidbrink
More informationComparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )
Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI
More informationKSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta
1 THS/P205 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis
More informationFirst plasma operation of Wendelstein 7X
First plasma operation of Wendelstein 7X R. C. Wolf on behalf of the W7X Team *) robert.wolf@ipp.mpg.de *) see author list Bosch et al. Nucl. Fusion 53 (2013) 126001 The optimized stellarator Wendelstein
More informationICRF Mode Conversion Flow Drive on Alcator CMod and Projections to Other Tokamaks
ICRF Mode Conversion Flow Drive on Alcator CMod and Projections to Other Tokamaks Y. Lin, J.E. Rice, S.J. Wukitch, M.J. Greenwald, A.E. Hubbard, A. Ince Cushman, L. Lin, E.S. Marmar, M. Porkolab, M.L.
More informationGA A26887 ADVANCES TOWARD QHMODE VIABILITY FOR ELMFREE OPERATION IN ITER
GA A26887 ADVANCES TOWARD QHMODE VIABILITY FOR ELMFREE OPERATION IN ITER by A.M. GAROFALO, K.H. BURRELL, M.J. LANCTOT, H. REIMERDES, W.M. SOLOMON and L. SCHMITZ OCTOBER 2010 DISCLAIMER This report was
More informationPlasma Spectroscopy Inferences from Line Emission
Plasma Spectroscopy Inferences from Line Emission Ø From line λ, can determine element, ionization state, and energy levels involved Ø From line shape, can determine bulk and thermal velocity and often
More informationAnalysis and modelling of MHD instabilities in DIIID plasmas for the ITER mission
Analysis and modelling of MHD instabilities in DIIID plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. PazSoldan 2, F. Carpanese 3, C.C. Petty 2, T.C.
More informationProgress Towards Confinement Improvement Using Current Profile Modification In The MST Reversed Field Pinch
Progress Towards Confinement Improvement Using Current Profile Modification In The MST Reversed Field Pinch C.B. Forest 1), J.K. Anderson 1), T.M. Biewer 1), D. Brower 2), B.E. Chapman 1), P.K. Chattopadhyay
More information1) Hmode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7X stellarator
MaxPlanckInstitut für Plasmaphysik 1) Hmode in Helical Devices M. Hirsch 1, T. Akiyama 2, T.Estrada 3, T. Mizuuchi 4, K. Toi 2, C. Hidalgo 3 1 MaxPlanckInstitut für Plasmaphysik, EURATOMAss., D17489
More informationPoS(ECPD2015)109. Planned Active Spectroscopy in the Neutral Beam Injectors of W7X
Planned Active Spectroscopy in the Neutral Beam Injectors of W7X Juergen Baldzuhn 1, Oliver Ford, Paul McNeely, Torsten Richert, W7X Team MaxPlanck Institut fuer Plasmaphysik, EURATOM Assoc., 17491
More informationGA A23698 ELECTRON CYCLOTRON WAVE EXPERIMENTS ON DIII D
GA A23698 ELECTRON CYCLOTRON WAVE EXPERIMENTS ON DIII D by C.C. PETTY, J.S. degrassie, R.W. HARVEY, Y.R. LINLIU, J.M. LOHR, T.C. LUCE, M.A. MAKOWSKI, Y.A. OMELCHENKO, and R. PRATER JUNE 21 DISCLAIMER
More informationSTABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK
GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This
More informationGA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D
GA A271 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D by C.C. PETTY, J.S. degrassie, R.W. HARVEY, Y.R. LINLIU, J.M. LOHR, T.C. LUCE, M.A. MAKOWSKI, Y.A. OMELCHENKO, and R. PRATER AUGUST 2001 DISCLAIMER This
More informationToroidal confinement devices
Toroidal confinement devices Dr Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th January 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 20) Last time... Power
More informationFast Ion Confinement in the MST Reversed Field Pinch
Fast Ion Connement in the MST Reversed Field Pinch Gennady Fiksel B. Hudson, D.J. Den Hartog, R.M. Magee, R. O'Connell, S.C. Prager MST Team  University of Wisconsin  Madison Center for Magnetic SelfOrganization
More informationOverview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations
Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER
More informationDIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by
UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN Presented by C.M. GREENFIELD for J.C. DeBOO, T.C. LUCE, B.W. STALLARD, E.J. SYNAKOWSKI, L.R. BAYLOR,3 K.H. BURRELL, T.A. CASPER, E.J.
More informationGA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS
GA A26247 EFFECT OF RESONANT AND NONRESONANT MAGNETIC BRAKING ON ERROR FIELD TOLERANCE IN HIGH BETA PLASMAS by H. REIMERDES, A.M. GAROFALO, E.J. STRAIT, R.J. BUTTERY, M.S. CHU, Y. In, G.L. JACKSON, R.J.
More informationELM Suppression in DIIID Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations
1 EXC/P502 ELM Suppression in DIIID Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science
More informationEffect of an error field on the stability of the resistive wall mode
PHYSICS OF PLASMAS 14, 022505 2007 Effect of an error field on the stability of the resistive wall mode Richard Fitzpatrick Institute for Fusion Studies, Department of Physics, University of Texas at Austin,
More informationObservation of Co and Counter Rotation Produced by Lower Hybrid Waves in Alcator CMod*
Observation of Co and Counter Rotation Produced by Lower Hybrid Waves in Alcator CMod* R. R. Parker, Y. Podpaly, J. Lee, M. L. Reinke, J. E. Rice, P.T. Bonoli, O. Meneghini, S. Shiraiwa, G. M. Wallace,
More informationLower Hybrid Current Drive Experiments on Alcator CMod: Comparison with Theory and Simulation
Lower Hybrid Current Drive Experiments on Alcator CMod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator CMod
More informationPhysics Considerations in the Design of NCSX *
1 IAEACN94/IC1 Physics Considerations in the Design of NCSX * G. H. Neilson 1, M. C. Zarnstorff 1, L. P. Ku 1, E. A. Lazarus 2, P. K. Mioduszewski 2, W. A. Cooper 3, M. Fenstermacher 4, E. Fredrickson
More informationTransport of Helium Impurity in Alcator CMod*
Transport of Helium Impurity in Alcator CMod* K. T. Liao, W. L. Rowan, I. O. Bespamyatnov, W. Horton, and X.R. Fu, R. Granetz, J. Hughes, Y. Ma, J. Walk Institute for Fusion Studies, The University of
More informationGA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D
GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D by J.S. degrassie, D.R. BAKER, K.H. BURRELL, C.M. GREENFIELD, H. IKEZI, Y.R. LINLIU, C.C. PETTY, and R. PRATER APRIL 1997 This report
More informationGA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFFAXIS NBI
GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFFAXIS NBI by J.M. HANSON, F. TURCO M.J. LANCTOT, J. BERKERY, I.T. CHAPMAN, R.J. LA HAYE, G.A. NAVRATIL, M. OKABAYASHI, H. REIMERDES, S.A. SABBAGH,
More informationRole of Magnetic Configuration and Heating Power in ITB Formation in JET.
Role of Magnetic Configuration and Heating Power in ITB Formation in JET. The JET Team (presented by V. Parail 1 ) JET Joint Undertaking, Abingdon, Oxfordshire, United Kingdom 1 present address: EURATOM/UKAEA
More informationStudies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D
Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of
More informationDensity Collapse in Improved Confinement Mode on Tohoku University Heliac
1 EX/P512 Density Collapse in Improved Confinement Mode on Tohoku University Heliac S. Kitajima 1), Y. Tanaka 2), H. Utoh 1), H. Umetsu 1), J. Sato 1), K. Ishii 1), T. Kobuchi 1), A. Okamoto 1), M. Sasao
More informationThe Role of Dynamo Fluctuations in Anomalous Ion Heating, Mode Locking, and Flow Generation
The Role of Dynamo Fluctuations in Anomalous Ion Heating, Mode Locking, and Flow Generation P. W. Terry 1), R. Gatto 1), R. Fitzpatrick 2), C.C. Hegna 3), and G. Fiksel 1) 1) Department of Physics, University
More information3D Reconstruction of Plasma Equilibria using Magnetic Diagnostics on the Compact Toroidal Hybrid. Benjamin Adam Stevenson
3D Reconstruction of Plasma Equilibria using Magnetic Diagnostics on the Compact Toroidal Hybrid by Benjamin Adam Stevenson A dissertation submitted to the Graduate Faculty of Auburn University in partial
More informationIntegrated Heat Transport Simulation of High Ion Temperature Plasma of LHD
1 TH/P638 Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD S. Murakami 1, H. Yamaguchi 1, A. Sakai 1, K. Nagaoka 2, H. Takahashi 2, H. Nakano 2, M. Osakabe 2, K. Ida 2, M. Yoshinuma
More informationEFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*
EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* by K.H. BURRELL Presented at the Transport Task Force Meeting Annapolis, Maryland April 3 6, 22 *Work supported by U.S. Department of Energy
More informationPlasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA
PFC/JA9528 Edge Turbulence Measurements during the L to HMode Transition by Phase Contrast Imaging on DIIIDt Coda, S.; Porkolab, M.; Plasma Fusion Center Massachusetts Institute of Technology Cambridge,
More informationHeating and Confinement Study of GlobusM Low Aspect Ratio Plasma
EX/P5 Heating and Confinement Study of GlobusM Low Aspect Ratio Plasma N.V. Sakharov ), V.V. Dyachenko ), B.B. Ayushin ), A.V. Bogomolov ), F.V. Chernyshev ), V.K. Gusev ), S.A. Khitrov ), N.A. Khromov
More informationThe Status of the Design and Construction of the Columbia Nonneutral Torus
The Status of the Design and Construction of the Columbia Nonneutral Torus J. P. Kremer,T.S.Pedersen,N.Pomphrey,W.Reiersen and F. Dahlgren Dept. of Applied Physics and Applied Mathematics, Columbia University,
More informationRecent results on noninductive startup of highly overdense ST plasma by electron Bernstein wave on LATE
Recent results on noninductive startup of highly overdense ST plasma by electron Bernstein wave on LATE M. Uchida, Y. Nozawa, H. Tanaka, T. Maekawa Graduate School of Energy Science, Kyoto University
More information