Present Status of TPE-RX Experiment

Size: px
Start display at page:

Download "Present Status of TPE-RX Experiment"

Transcription

1 Present Status of TPE-RX Experiment IEA RFP Workshop at Madison 28 Feb. - 1 Mar. 2 Y.Hirano, Y. Yagi, T.Shimada, S. Sekine, H.Sakakita, H.Koguchi, Y.Maejima, S.Kiyama, Y.Sato, K.Hayase

2 Reversed Field Pinch Machine, TPE-RX R / a = m /.45m, Vol. = 7 m 3 Designed Max. Ip = 1MA, t dis = <1 ms Aims of TPE-RX To find a way to improve RFP confinement. Vloop <1V & bp >.1 in the same time => t E = 5-1 ms

3 Recent Activities of TPE-RX Almost two years since experiment start (March 1998). 1. Operation range, Ip <~5kA, duration up to 1ms with ~22kA 2. Temperature Measurement and Estimation of bp, tau-e, etc. High Te ~ 64 ev, medium Ti ~ 32eV with low ne ~ 5E18/m3 bp ~ 6-1%, tau-e ~.5-1ms (will be presented by Dr. Yagi) 3. Analysis of locked mode (will be presented by Dr. Yagi) Magnetic, Spectroscopy, Halo current measurement Comparison of discharges with and without locked mode. 4. Spectroscopy Plasma rotation, Toroidal & poloidal radiation profile. 5. Density Control by Gas Puff 6. Trial of PPCD

4 Typical RFP Plasma in TPE-RX Ip = 26kA, Rp*Ip ~ 15V, duration 9ms Without locking mode, Rp (micro ohm) F, Theta Shot Voh=5/1.4kV, Vtf=4.8//.25kV, p=.4mtorr <Bt> 1 <Ip> <Vloop> 5 Rp (micro ohm) 25 <Rp*Ip> Btwi Btwo t (ms) Theta F 2 4 t (ms) Btwo, Btwi, <Bt> (mt) Vloop, Rp*Ip (volt)

5 The longest discharge Ip-peak ~ 2kA & 1ms duration ka VL RpIp rxiv1346.dat Bt_ave Btw 2 4 t (ms) Ip Theta F t (ms) V, mt

6 Variation of Non-inductive Part of Variation of Vloop with shot mber and Ip RpIp now stays almost constant level, (~1-2V at Ip~25kA) Situation that Vloop increases with Ip does not change. Further wall conditioning (Ti gettering and/or Boronization)?? Rp*Ip (V) 5V Decay phase With DC Ver. 2V 15V 15V 5V 4 shot No. V 12 2kA All shots except Ip<1kA, t=32.5ms 4kA

7 Reduction of RpIp by DC Bv From 17-18V to 13-15V at Ip27kA Ip(kA) RpIp(V) I-DCV Scan. Voh=5/1.4, Vtf=5// V at 9G ms ms Ip (A) Ip (25A) ( G) Ip (3A) ( 11G) Ip (35A) ( 13G) Ip (5A) ( 18G) BDCV 36G/kA

8 Reduction of RpIp in Ip decay phase From 17-18V to 1V at Ip24kA IpRp (V) t (ms) dip/dt Scan. t = 4ms -1 Ip*Rp (volt) 2 1 Idcv= RpIp = 1V Idcv = 25A dip/dt (ka/ms)

9 Discharges without locked mode and with locked mode Marginal conditions at Ip ~ 25kA Duration is longer and SBD is larger without LM. 4 Ip 3 SBD rxiv14695.dat 4 SX 3 4 Ip 3 rxiv14676.dat 4 SX Vloop (V) SBD Vloop (V) t (ms) t (ms)

10 Shortening of discharge duration by the Locked Mode But it shows little effect on RpIp at the time of locking locking in the midle No locking of discharge 1 early locking IV_1213_9_LM 8 Ip RpIp t (ms) IpRp (V) no locking rxiv Theta 2 SBD F Locking from t<~2ms No clear difference before locking Clear difference in SBD but little difference in Ip, RpIp, F after locking except before termination. Theta with locking < that w/o locking

11 Plasma Rotation in TPE-RX Toroidal velocity [km/s] Plasma current [ka] Plasma current direction Net toroidal plasma rotation velocities of C 4+ ions around r/a~.9 as a function of the plasma current. Solid symbols show the locked mode cases. Cross symbol shows an unlocked case. Radial electric field (E r ) [kv/m] ρ L / L H. Sakakita, Y. Yagi et al.; J. Phys. Soc. Jpn. Vol. 69, No. 3 (2).

12 Radial profile of CV (227.1nm) line radiation Fitting function ; y = exp[c2{(r/a) - C1}] - exp[c4{(r/a) - C3] + C5 Intensity(Arb.U.)Intensity(Arb.U.) r (m) Raw data (chord integration) After inversion S.Sekine, T. Osakabe. et.al., Journal of Plasma Fusion Research, Vol.2(1999)192

13 Density Control by the Gas Puff, No fatal effect on discharge Increase of <ne>.4e19 =>.7E19 => 1.5E19 /m 3 at Ip ~ 27kA <ne> E2/m No Gas Puffing nli ~.4 E19/m t (ms).3.25 nli With one medium GAS Puffing.1 ~.7 E19/m <ne> E2/m nli With two strong GAS Puffings.15.1 ~ 1.5 E19/m <Bt> 3 75 Ip 2 Vloop 5 RpIp 1 25 Btw-out Btw-in t (ms) 4 <Bt> Vloop Ip 5 1 RpIp 25 Btw-out Btw-in <Bt> 75 2 Ip 5 Vloop 1 RpIp 25 Btw-out Btw-in Bt (mt), RpIp (V), Vloop (V) Bt (mt), RpIp (V), Vloop (V) Bt (mt), RpIp (V), Vloop (V)

14 Density control with Gas Puff in TPE-RX Gas Puff nls14143, Gas Puff at t=25ms (two puffs) <ne> (E2/m3) time (ms) 2 1 Vloop SX (A.U.) rxiv14143.dat 1 SX.5 Btw (mt) time (ms)

15 DMR (Deep Magnetic field Reversal) Exp. in TPE-RX (Initial PPCD Exp.) Plasma current [ka] PPCD Increase of SX SBD Btw_out time [ms] I P F-Theta curve becomes close to relaxed state in Fast Btw reversal. Both radial magnetic fluctuations and D a intensity at r/a~.9 are suppressed. Toroidal plasma rotation velocity (C 4+ ions) shows no extinct behavior in the present conditions SBD [a. u.] F rxiv1558_96_99_abr1.dat Fast Bt Rev. PPCD t=15-25ms Slow Bt Rev. Medium Bt Rev Theta

16 Summary Almost two years since experiment start 1. Max. Ip ~5kA. Max t-dis ~1ms for Ip ~ 22kA. 2. High Te (<~1eV) is realized with low density (~5E18/m 3 ) Similar to TPE-1RM2 & 1RM15. High I/N ~1-13 A/m 3. RpIp has not been reduced to < 1V, remains at high value ~15V Vloop anomaly is ~ 5% of RpIp (H~1 & Zeff~5 are assumed) 4. Comparison of discharges with and w/o locked mode. LM causes strong PWI; reducing t-dis & limiting high Ip Op. 5. Plasma rotation depends on Ip (5km/s at Ip~2kA, at 37kA) 6. Density control is successfully done. ne can go up to 3E19/m 3 7. PPCD seems to be promising, sharp increase of SX(Te & ne) Further investigation is planned.

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Evaluation of CT injection to RFP for performance improvement and reconnection studies Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi

More information

Reduction of fluctuations and edge current during PPCD in MST. B. E. Chapman and the MST group

Reduction of fluctuations and edge current during PPCD in MST. B. E. Chapman and the MST group Reduction of fluctuations and edge current during PPCD in MST B. E. Chapman and the MST group Outline -- The key to sustained fluctuation reduction during PPCD -- Magnetic fluctuations (including single

More information

Impurity expulsion in an RFP plasma and the role of temperature screening

Impurity 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 Wisconsin-Madison, Madison,Wisconsin,

More information

The Li-wall Stellarator Experiment in TJ-II

The Li-wall Stellarator Experiment in TJ-II The Li-wall Stellarator Experiment in TJ-II Laboratorio Nacional de Fusión. CIEMAT. Madrid. Spain Outlook Introduction Why Lithium? Li coating technique in TJ-II 2008 Results Particle recycling and confinement

More information

Density Fluctuation Induced Kinetic Dynamo and Nonlinear Tearing Mode Saturation in the MST Reversed Field Pinch

Density Fluctuation Induced Kinetic Dynamo and Nonlinear Tearing Mode Saturation in the MST Reversed Field Pinch Density Fluctuation Induced Kinetic Dynamo and Nonlinear Tearing Mode Saturation in the MST Reversed Field Pinch W.X.Ding, L. Lin, D.L. Brower, A. Almagri, B. Chapman, G. Fiksel, D.J. Den Hartog, J. Reusch,

More information

CONFINEMENT IN THE RFP: LUNDQUIST NUMBER SCALING, PLASMA FLOW, AND REDUCED TRANSPORT

CONFINEMENT 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 C-S. Chiang, 1 B.E. Chapman, 1 J.T. Chapman,

More information

First Quantification of Electron Thermal Transport in the MST Reversed-Field Pinch

First Quantification of Electron Thermal Transport in the MST Reversed-Field Pinch First Quantification of Electron Thermal Transport in the MST Reversed-Field Pinch Title Abs. TS over. MStFIt j 2kA Te ne Zeff 4kA Te ne Zeff Pohm, W, TauE,beta Xe,D Mot. FIR pola. Monte Carlo Un. An.

More information

Progress 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 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 information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,

More information

The Effects of Noise and Time Delay on RWM Feedback System Performance

The Effects of Noise and Time Delay on RWM Feedback System Performance The Effects of Noise and Time Delay on RWM Feedback System Performance O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York,

More information

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control

Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.

More information

Electron Thermal Transport Within Magnetic Islands in the RFP

Electron Thermal Transport Within Magnetic Islands in the RFP Electron Thermal Transport Within Magnetic Islands in the RFP Hillary Stephens University of Wisconsin Madison APS-DPP Meeting November 3, 2009 J.R. Amubel, M.T. Borchardt, D.J. Den Hartog, C.C. Hegna,

More information

Current Drive Experiments in the HIT-II Spherical Tokamak

Current Drive Experiments in the HIT-II Spherical Tokamak Current Drive Experiments in the HIT-II Spherical Tokamak T. R. Jarboe, P. Gu, V. A. Izzo, P. E. Jewell, K. J. McCollam, B. A. Nelson, R. Raman, A. J. Redd, P. E. Sieck, and R. J. Smith, Aerospace & Energetics

More information

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Observation of Neo-Classical Ion Pinch in the Electric Tokamak* 1 EX/P6-29 Observation of Neo-Classical 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 information

Phase ramping and modulation of reflectometer signals

Phase ramping and modulation of reflectometer signals 4th Intl. Reflectometry Workshop - IRW4, Cadarache, March 22nd - 24th 1999 1 Phase ramping and modulation of reflectometer signals G.D.Conway, D.V.Bartlett, P.E.Stott JET Joint Undertaking, Abingdon, Oxon,

More information

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK

Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK C. Silva, H. Figueiredo, J.A.C. Cabral,, I. Nedzelsky, C.A.F. Varandas Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior

More information

Current Profile Control by ac Helicity Injection

Current Profile Control by ac Helicity Injection Current Profile Control by ac Helicity Injection Fatima Ebrahimi and S. C. Prager University of Wisconsin- Madison APS 2003 Motivations Helicity injection is a method to drive current in plasmas in which

More information

Progress of Confinement Physics Study in Compact Helical System

Progress of Confinement Physics Study in Compact Helical System 1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress

More information

The RFP: Plasma Confinement with a Reversed Twist

The RFP: Plasma Confinement with a Reversed Twist The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of Wisconsin-Madison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed

More information

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport*

Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* Enhanced Energy Confinement Discharges with L-mode-like Edge Particle Transport* E. Marmar, B. Lipschultz, A. Dominguez, M. Greenwald, N. Howard, A. Hubbard, J. Hughes, B. LaBombard, R. McDermott, M. Reinke,

More information

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff

A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development

More information

AC loop voltages and MHD stability in RFP plasmas

AC loop voltages and MHD stability in RFP plasmas AC loop voltages and MHD stability in RFP plasmas K. J. McCollam, D. J. Holly, V. V. Mirnov, J. S. Sar, D. R. Stone UW-Madison 54rd Annual Meeting of the APS-DPP October 29th - November 2nd, 2012 Providence,

More information

The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak

The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak The measurement of plasma equilibrium and fluctuations near the plasma edge using a Rogowski probe in the TST-2 spherical tokamak H. Furui, Y. Nagashima 2, A. Ejiri, Y. Takase, N. Tsujii, C. Z. Cheng,

More information

Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak

Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak P6-29 Soft X-ray emission profile and mode structure during MHD events in the TST-2 spherical tokamak H.Tojo, A.Ejiri, Y.Takase, Y.Torii, T.Osako, M.Sasaki (1), T.Masuda, Y.Shimada N.Sumitomo (1), J.Tsujimura,

More information

Fast Ion Confinement in the MST Reversed Field Pinch

Fast 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 Self-Organization

More information

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection

1 IC/P4-5. Spheromak Formation by Steady Inductive Helicity Injection 1 IC/P4-5 Spheromak Formation by Steady Inductive Helicity Injection T. R. Jarboe, C. Akcay, W. T. Hamp, R. Z. Aboul Hosn, G. J. Marklin, B. A. Nelson, R. G. O Neill, P. E. Sieck, R. J. Smith, and J. S.

More information

Lower Hybrid Wave Induced Rotation on Alcator C-Mod* Ron Parker, Yuri Podpaly, John Rice, Andréa Schmidt

Lower Hybrid Wave Induced Rotation on Alcator C-Mod* Ron Parker, Yuri Podpaly, John Rice, Andréa Schmidt Lower Hybrid Wave Induced Rotation on Alcator C-Mod* Ron Parker, Yuri Podpaly, John Rice, Andréa Schmidt *Work supported by USDoE awards DE-FC-99ER551 and DE-AC-7CH373 Abstract Injection of RF power in

More information

Oscillating-Field Current-Drive Experiment on MST

Oscillating-Field Current-Drive Experiment on MST Oscillating-Field Current-Drive 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 Wisconsin-Madison D.

More information

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center

OVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power

More information

The 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 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 information

Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations

Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations Measurements of Core Electron Temperature Fluctuations in DIII-D with Comparisons to Density Fluctuations and Nonlinear GYRO Simulations A.E. White,a) L. Schmitz,a) G.R. McKee,b) C. Holland,c) W.A. Peebles,a)

More information

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS GA A25488 PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS by D.A. HUMPHREYS, D.G. WHYTE, M. BAKHTIARI, R.D. DERANIAN, E.M. HOLLMANN, A.W. HYATT, T.C. JERNIGAN, A.G.

More information

Oscillating Field Current Drive on MST

Oscillating Field Current Drive on MST Oscillating Field Current Drive on MST John Sarff A. Blair, K. McCollam, P. Nonn, J. Anderson, D. Brower 1, D. Craig, B. Deng 1, D. Den Hartog, W. Ding 1, F. Ebrahimi, D. Ennis, G. Fiksel, S. Gangadhara,

More information

First Experiments in SST-1

First Experiments in SST-1 First Experiments in SST-1 Subrata Pradhan & SST-1 Team Institute for Plasma Research India OV 5-5 Steady State Superconducting Tokamak (SST-1) at IPR Outline SST-1 Parameters Results in SST-1 from Engineering

More information

THE ADVANCED TOKAMAK DIVERTOR

THE ADVANCED TOKAMAK DIVERTOR I Department of Engineering Physics THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and the team 14th PSI QTYUIOP MA D S O N UCLAUCLA UCLA UNIVERSITY OF WISCONSIN THE ADVANCED TOKAMAK DIVERTOR S.L. Allen and

More information

Abstract. Department of Physics. University of Wisconsin UCLA UCLA

Abstract. Department of Physics. University of Wisconsin UCLA UCLA Abstract Internal magnetic field fluctuations and equilibrium poloidal magnetic field have been measured in the MST reversal field pinch by a 11 chord far-infrared polarimeterinterferometer system with

More information

Comparison 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 ) 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 information

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD

Integrated Heat Transport Simulation of High Ion Temperature Plasma of LHD 1 TH/P6-38 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 information

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU

Edge and Internal Transport Barrier Formations in CHS. Identification of Zonal Flows in CHS and JIPPT-IIU Edge and Internal Transport Barrier Formations in CHS S. Okamura, T. Minami, T. Akiyama, T. Oishi, A. Fujisawa, K. Ida, H. Iguchi, M. Isobe, S. Kado, K. Nagaoka, K. Nakamura, S. Nishimura, K. Matsuoka,

More information

Integrated Particle Transport Simulation of NBI Plasmas in LHD )

Integrated 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 information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod

Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod Evaluation of Anomalous Fast-Ion Losses in Alcator C-Mod S. D. Scott Princeton Plasma Physics Laboratory In collaboration with R. Granetz, D. Beals, M. Greenwald MIT PLASMA Science and Fusion Center W.

More information

Ion 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 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 information

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device Production of Over-dense Plasmas by Launching 2.45GHz Electron Cyclotron Waves in a Helical Device R. Ikeda a, M. Takeuchi a, T. Ito a, K. Toi b, C. Suzuki b, G. Matsunaga c, S. Okamura b, and CHS Group

More information

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Yasuhiro KAMINOU, Michiaki INOMOTO and Yasushi ONO Graduate School of Engineering, The

More information

University of Washington

University of Washington Aerospace and Energetics Research Program University of Washington Seattle, WA 44th Annual Meeting of the Division of Plasma Physics of the American Physical Society November 11 - November 15, 2002 Orlando,

More information

Operational Phase Space of the Edge Plasma in Alcator C-Mod

Operational Phase Space of the Edge Plasma in Alcator C-Mod Operational Phase Space of the Edge Plasma in B. LaBombard, T. Biewer, M. Greenwald, J.W. Hughes B. Lipschultz, N. Smick, J.L. Terry, Team Contributed talk RO.00008 Presented at the 47th Annual Meeting

More information

Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus

Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus Evidence for Magnetic Relaxation in Coaxial Helicity Injection Discharges in the HIT II Spherical Torus A. J. Redd Aerospace & Energetics Research University of Washington Seattle, Washington USA 24 Innovative

More information

Flow and dynamo measurements in the HIST double pulsing CHI experiment

Flow and dynamo measurements in the HIST double pulsing CHI experiment Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.

More information

Axial symmetric open magnetic traps with depressed transversal losses of plasmas

Axial symmetric open magnetic traps with depressed transversal losses of plasmas Axial symmetric open magnetic traps with depressed transversal losses of plasmas A. Sidorov, S. Golubev, I. Izotov, S. Razin, V. Skalyga and A. Vodopyanov Institute of Applied Physics, RAS, 603950 Nizhny

More information

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139

Alcator C-Mod. Double Transport Barrier Plasmas. in Alcator C-Mod. J.E. Rice for the C-Mod Group. MIT PSFC, Cambridge, MA 02139 Alcator C-Mod Double Transport Barrier Plasmas in Alcator C-Mod J.E. Rice for the C-Mod Group MIT PSFC, Cambridge, MA 139 IAEA Lyon, Oct. 17, Outline Double Barrier Plasma Profiles and Modeling Conditions

More information

A New Method of Measuring the Magnetic Field in Hot Plasmas Using Helium Neutral Beam Injection

A New Method of Measuring the Magnetic Field in Hot Plasmas Using Helium Neutral Beam Injection A New Method of Measuring the Magnetic Field in Hot Plasmas Using Helium Neutral Beam Injection Yoichi HIRANO, Benjamin HUDSON 1,a), Haruhisa KOGUCHI, Hajime SAKAKITA and Satoru KIYAMA Plasma Frontier

More information

Characteristics of Energetic-Ion-Driven Geodesic Acoustic Modes in the Large Helical Device(LHD)

Characteristics of Energetic-Ion-Driven Geodesic Acoustic Modes in the Large Helical Device(LHD) O-4 12 th IAEA TM on Energetic Particles in Magnetic Confinement Systems, 7-10 Sep, Austin, USA Characteristics of Energetic-Ion-Driven Geodesic Acoustic Modes in the Large Helical Device(LHD) K. Toi,

More information

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

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 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 information

ICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod

ICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod ICRF Induced Argon Pumpout in H-D Plasmas in Alcator C-Mod C. Gao, J.E. Rice, M.L. Reinke, Y. Lin, S.J. Wukitch, L. Delgado-Aparicio, E.S. Marmar, and Alcator C-Mod Team MIT-PSFC, University of York, Princeton

More information

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges

Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Aaron J. Redd for the Pegasus Team 2008 Innovative Confinement Concepts Workshop Reno, Nevada June 24-27,

More information

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics Z. Yan 1, G.R. McKee 1, J.A. Boedo 2, D.L. Rudakov 2, P.H. Diamond 2, G. Tynan 2, R.J. Fonck 1, R.J. Groebner 3, T.H. Osborne 3, and

More information

Understanding Turbulence is a Grand Challenge

Understanding Turbulence is a Grand Challenge The Turbulent Structure of a Plasma Confined by a Magnetic Dipole B. A. Grierson M.W. Worstell, M.E. Mauel ICC 28 Reno, NV 1 Understanding Turbulence is a Grand Challenge Ubiquitous in natural and laboratory

More information

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D GA A24724 FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D by D.L. RUDAKOV, J.A. BOEDO, R.A. MOYER, N.H. BROOKS, R.P. DOERNER, T.E. EVANS, M.E. FENSTERMACHER, M. GROTH, E.M. HOLLMANN, S. KRASHENINNIKOV,

More information

Ion Temperature Measurements in the

Ion Temperature Measurements in the Ion Temperature Measurements in the PEGASUS Toroidal Experiment M.G. Burke, M.W. Bongard, R.J. Fonck, D.J. Schlossberg, A.J. Redd 52 nd Annual APS-DPP University of Wisconsin-Madison Chicago, IL November

More information

Electrode Biasing Experiment in the Large Helical Device

Electrode Biasing Experiment in the Large Helical Device 1 EXC/P8-07 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 information

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS

SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-10 TOKAMAK PLASMAS SUMMARY OF EXPERIMENTAL CORE TURBULENCE CHARACTERISTICS IN OH AND ECRH T-1 TOKAMAK PLASMAS V. Vershkov, L.G. Eliseev, S.A. Grashin. A.V. Melnikov, D.A. Shelukhin, S.V. Soldatov, A.O. Urazbaev and T-1 team

More information

Confinement of toroidal non-neutral plasma

Confinement of toroidal non-neutral plasma 10th International Workshop on Non-neutral Plasmas 28 August 2012, Greifswald, Germany 1/20 Confinement of toroidal non-neutral plasma in magnetic dipole RT-1: Magnetospheric plasma experiment Visualized

More information

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg

A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg A.J.Redd, D.J.Battaglia, M.W.Bongard, R.J.Fonck, and D.J.Schlossberg 51st APS-DPP Annual Meeting November 2-6, 2009 Atlanta, GA USA The PEGASUS Toroidal Experiment Helicity injection in PEGASUS Testing

More information

Transport Improvement Near Low Order Rational q Surfaces in DIII D

Transport 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 information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

Plasma Flow in MST: Effects of Edge Biasing and Momentum Transport from Nonlinear Magnetic Torques

Plasma Flow in MST: Effects of Edge Biasing and Momentum Transport from Nonlinear Magnetic Torques Plasma Flow in MST: Effects of Edge Biasing and Momentum Transport from Nonlinear Magnetic Torques J.S. Sarff, A.F. Almagri, J.K. Anderson, B.E. Chapman, D. Craig, C-S. Chiang, N.A. Crocker, D.J. Den Hartog,

More information

Expanding Non-Solenoidal Startup with Local Helicity Injection

Expanding Non-Solenoidal Startup with Local Helicity Injection Expanding Non-Solenoidal Startup with Local Helicity Injection Justin M. Perry J. L. Barr, G. M. Bodner, M. W. Bongard, M. G. Burke, R. J. Fonck, E. T. Hinson, B. T. Lewicki, J. A. Reusch, D. J. Schlossberg

More information

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS Presented by D.P. SCHISSEL Presented to APS Centennial Meeting March 20 26, 1999 Atlanta, Georgia

More information

High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac

High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac J. Plasma Fusion Res. SERIES, Vol. 8 (2009) High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac Hiroyasu UTOH, Kiyohiko NISHIMURA 1), Hajime UMETSU, Keiichi ISHII,

More information

Predicting the Rotation Profile in ITER

Predicting the Rotation Profile in ITER Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton

More information

HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM

HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM GA A24391 HIFLUX: OBLATE FRCs, DOUBLE HELICES, SPHEROMAKS AND RFPs IN ONE SYSTEM by M.J. SCHAFFER and J.A. BOEDO JULY 2003 QTYUIOP DISCLAIMER This report was prepared as an account of work sponsored by

More information

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

STABILIZATION 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 information

Non-Solenoidal Plasma Startup in

Non-Solenoidal Plasma Startup in Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique

More information

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U 1 EX/P4-25 Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-6U T. Nakano, H. Kubo, N. Asakura, K. Shimizu and S. Higashijima Japan Atomic Energy Agency, Naka,

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D 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 information

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D GA A443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D by R.J. GROEBNER, T.N. CARLSTROM, K.H. BURRELL, S. CODA, E.J. DOYLE, P. GOHIL, K.W. KIM, Q. PENG, R. MAINGI, R.A. MOYER, C.L. RETTIG, T.L. RHODES,

More information

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

Density Collapse in Improved Confinement Mode on Tohoku University Heliac 1 EX/P5-12 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 information

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas 1 EX/P5-4 Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas J.E. Rice 1), A.C. Ince-Cushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke

More information

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation 1 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation Y. Nakashima1), Y. Higashizono1), H. Kawano1), H. Takenaga2), N. Asakura2), N. Oyama2),

More information

Confinement of toroidal non-neutral plasma in Proto-RT

Confinement of toroidal non-neutral plasma in Proto-RT Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,

More information

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

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 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 Non-solenoidal startup using point-source DC helicity injectors

More information

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS

RESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS RESISTIVE WALL MODE STABILIZATION RESEARCH ON STATUS AND RECENT RESULTS by A.M. Garofalo1 in collaboration with J. Bialek,1 M.S. Chance,2 M.S. Chu,3 T.H. Jensen,3 L.C. Johnson,2 R.J. La Haye,3 G.A. Navratil,1

More information

Confinement of toroidal non-neutral plasma in Proto-RT

Confinement of toroidal non-neutral plasma in Proto-RT Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,

More information

Studies of Turbulence and Transport in Alcator C- Mod H-Mode Plasmas with Phase Contrast Imaging and Comparisons with GYRO*

Studies of Turbulence and Transport in Alcator C- Mod H-Mode Plasmas with Phase Contrast Imaging and Comparisons with GYRO* Studies of Turbulence and Transport in C- Mod H-Mode Plasmas with Phase Contrast Imaging and Comparisons with GYRO* M. Porkolab 1, L. Lin 1, E.M. Edlund 1, J.C. Rost 1, C.L. Fiore 1, M. Greenwald 1, Y.

More information

Behavior of Compact Toroid Injected into the External Magnetic Field

Behavior of Compact Toroid Injected into the External Magnetic Field Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa

More information

Two Fluid Dynamo and Edge-Resonant m=0 Tearing Instability in Reversed Field Pinch

Two Fluid Dynamo and Edge-Resonant m=0 Tearing Instability in Reversed Field Pinch 1 Two Fluid Dynamo and Edge-Resonant m= Tearing Instability in Reversed Field Pinch V.V. Mirnov 1), C.C.Hegna 1), S.C. Prager 1), C.R.Sovinec 1), and H.Tian 1) 1) The University of Wisconsin-Madison, Madison,

More information

Prospects for Driven Particle Convection Tests in LDX. Abstract

Prospects for Driven Particle Convection Tests in LDX. Abstract Prospects for Driven Particle Convection Tests in LDX M.E. Mauel, A.C. Boxer, J.L. Ellsworth, D.T. Garnier, J. Kesner Columbia University and Plasma Science and Fusion Center, MIT 49th Meeting of the APS

More information

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment

Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment Internal Magnetic Field Measurements and Langmuir Probe Results for the HIT-SI Experiment (First Evidence of Spheromak Generation and Sustainment) Roger J. Smith Plasma Dynamics Group University of Washington,

More information

Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal

Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal Particle Transport and Density Gradient Scale Lengths in the Edge Pedestal W. M. Stacey Fusion Research Center, Georgia Institute of Technology, Atlanta, GA, USA Email: weston.stacey@nre.gatech.edu Abstract

More information

Abstract. Introduction TH/P3-2. contact of main author:

Abstract. Introduction TH/P3-2.  contact of main author: TH/P- Runaway Electron Generation during Plasma Shutdown by Killer Pellet Injection K. Gál(), H Smith(), T. Fülöp() and P Helander() () KFKI-RMKI, Association EURATOM, Budapest () Department of Radio and

More information

Role of Low-Order Rational Surfaces in Transport Barrier Formation on the Large Helical Device

Role of Low-Order Rational Surfaces in Transport Barrier Formation on the Large Helical Device Role of Low-Order Rational Surfaces in Transport Barrier Formation on the Large Helical Device K. Toi, F. Watanabe a, K. Tanaka, T. Tokuzawa, K. Ogawa b, M. Isobe, M. Osakabe, Y. Suzuki, T. Akiyama, K.

More information

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission

Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 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 information

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment Derivation of dynamo current drive and stable current sustainment in the HIT SI experiment 1 Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment

More information

ICRF Induced Argon Pumpout in H-D Plasmas at Alcator C-Mod

ICRF Induced Argon Pumpout in H-D Plasmas at Alcator C-Mod 0 ICRF Induced Argon Pumpout in H-D Plasmas at Alcator C-Mod C Gao J.E. Rice, M.L. Reinke, S.J. Wukitch, Y. Lin and Alcator C-Mod Team MIT-PSFC October 29, 2014 C Gao etc., MIT-PSFC 56th APS-DPP New Orleans,

More information

Additional Heating Experiments of FRC Plasma

Additional Heating Experiments of FRC Plasma Additional Heating Experiments of FRC Plasma S. Okada, T. Asai, F. Kodera, K. Kitano, T. Suzuki, K. Yamanaka, T. Kanki, M. Inomoto, S. Yoshimura, M. Okubo, S. Sugimoto, S. Ohi, S. Goto, Plasma Physics

More information

ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation

ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation A. Bader 1, P. Bonoli 1, R. Granetz 1, R.W. Harvey 2, E.F. Jaeger 3, R. Parker 1, S. Wukitch 1. 1)MIT-PSFC, Cambridge,

More information

Improved absolute calibration of core Thomson scattering(ts) diagnostics on Alctor C-Mod

Improved absolute calibration of core Thomson scattering(ts) diagnostics on Alctor C-Mod Improved absolute calibration of core Thomson scattering(ts) diagnostics on Alctor C-Mod Yunxing Ma, J.W.Hughes, A.Hubbard MIT Plasma Science and Fusion Center Presented at 2008 APS DPP Conference Dallas,

More information

Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA

Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA PFC/JA-95-28 Edge Turbulence Measurements during the L- to H-Mode Transition by Phase Contrast Imaging on DIII-Dt Coda, S.; Porkolab, M.; Plasma Fusion Center Massachusetts Institute of Technology Cambridge,

More information