Development of Net-Current Free Heliotron Plasmas in the Large Helical Device

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

Download "Development of Net-Current Free Heliotron Plasmas in the Large Helical Device"

Transcription

1 Development of Net-Current Free Heliotron Plasmas in the Large Helical Device A. Komori for the LHD Experimental Group National Institute for Fusion Science Toki, Japan 22nd IAEA Fusion Energy Conference Geneva, October,1/17 28

2 Reactor relevant net-current free plasmas in LHD ASDEX MAST Unique test bed for high-performance steady state plasmas & 3-D study Large commonality with tokamaks 2/17

3 Outline _ 1. High ion temperature 6.8 kev at ne = 2 119m-3 with confinement improvement similar to ITB accompanied by Impurity hole 2. High beta <β> = 5 %, <β> > 4.5 % for > 1τE 3. High density ne () = m-3 at B = 2.5 T with Internal Diffusion Barrier (IDB) in Helical Divertor 4. Steady state 5. Summary EX: 22 papers, TH: 8 papers, FT: 4 papers in this conference Please visit these studies for details on transport, MHD stability, fast Ions, AE, heating physics, divertor, PSI, dust and reactor design 3/17

4 New perpendicular NBI much improves ion transport study - High-power NBI of 23 MW in total 4 beam lines of NBI = 3 tangential + 1 perpendicular ( + 1 perpendicular in 21) Tangential beams 18keV-tangential NB injector Perpendicular beam NBI 7 MW, E = 4kV with positive-ion sources i 4keV-perpendicular NB injector Ion heating (T () = 6.8 kev) works as a diagnostic beam for 4/17

5 Improvement of ion heat transport realized by upgrade of ion heating power _ 8 8 Pi=6.5~1MW 6 Ti (kev) Ti() (kev) Pi=2.5~5MW 1 3 _2 ne (119 m-3) ρ Above Pi / ni > MW m3 (Fri) EX/8-2Ra by Nagaoka 5/17

6 Ion thermal transport is improved significantly in ITB phase χ i_exp(w/o ITB) 1 1 χ i (m2/s) i 2 χ (m /s) χ i_exp(itb) χ i_nc(itb) 1 ρ =.3 ρ =.8 χ i_nc(w/o ITB).2.4 ρ Pi/ni (MW/119m-3) Anomalous transport is suppressed in the ITB phase NC analysis suggests large negative Er (Ion root) (Fri) EX/8-2Ra by Nagaoka 6/17

7 Carbon impurity is expelled due to outward convection in ITB phase : Impurity Hole t=1.25s 1..3 ncvi (119 m-3) 1.5 t=1.65s R (m) t=1.25s t=1.65s ncvi (119 m-3) ne (119m-3) R (m) More hollow as the ion temperature gradient is increased Steep Ti gradient Extremely hollow carbon profile impurity hole, which is quite different from electron density profile. Contradicting NC prediction suggests anomalous convection (Fri) EX/8-2Rb by Ida 7/17

8 β of 5 % has been achieved and β of 4.5 % has been maintained in steady state 3-D equilibrium calculated by HINT 5 <β > (%) <β > > 3.5 % 5 τ duration 1 /τ 15 E Beta limit Transport in the ergodic layer Change of magnetic topology, e.g., magnetic island dynamics Effect of stochasticity has been investigated in detail (Wed) EX/P5-9 by Weller, (Fri) EX/8-1Rb by Ohdachi, TH/P9-19 by Suzuki 8/17

9 High-β Operational Regime Standard Scenario IDB Scenario Sa (Fri) EX/8-1Rb by Ohdachi Co ll th o o wt ap se Ap = 6.6 (25~) Ap = 6.3 (24) Ap = 5.8 (~23) Magnetic axis position is a key parameter for high-beta Standard Scenario (broad pressure profile) - restrict the plasma outward shift to maintain good heating efficiency at low-field increase plasma aspect ratio <β> = 5 %, β ~ 1 % IDB Scenario (peaked pressure profile) - overcome the core density collapse <β> = 2 %, β ~ 1 % 9/17

10 Interaction between Alfvén eigenmodes and energetic-particles in LHD TAE-induced fast-ion loss measurement with scintillator probe (SLIP) Analysis in collaboration (Fri) EX/P8-5 by Nishiura with AE3D code (Thu) TH/3-4 by Spong (ORNL) Impact of Alfvén eigemodes on GAM (Fri) EX/P8-4 by Toi Understanding of RSAE freq. sweeping with MHD theory (Fri) EX/P8-4 by Toi Phase space structure analysis of TAE-induced fast-ion transport (Tue) TH/P3-9 by Todo 1/17

11 Achievements of High Density, High Pressure Discharges with Internal Diffusion Barrier e 21-3 Maximum n () exceeds 1 1 m Maximum P() =13 kpa Pressure is limited (Fri)rise EX/8-1Rb byby Ohdachi Core Density Collapse (CDC) CDC mitigated by elongation P() = 15 kpa IDB widens as the preset magnetic axis is moved outward and IDB foot extends to LCFS with Rax= 4. m LCFS IDB foot shifted axis max. ne() κ optimized max. P() IDB formation 11/17

12 Diffusion Coefficient kept at tolerable level under large density gradient due to IDB Relationship between time evolution and gradient of density profiles Core plasma a (pressure rise): dne/dρ increases with IDB formation, D.5 m2/s b (maximum pressure): flux increase without dne/dρ change c (pressure decline): dne/dρ decrease with density decay, D.5 m2/s Mantle plasma A (IDB formation period): Can not reach large dne/dρduring high flux IDB phase, D.43 m2/s (after IDB disappearance): merge into c, D.5 m2/s Thermal transport is unaffected by particle transport (Fri) EX/8-1Ra by Sakamoto 12/17

13 Transport in ergodic layer is a key to high-performance high density plasmas reff (m) LC/m Te/eV 1 Core plasma is surrounded by ergodic layer due to stretching and folding of magnetic islands Edge surface layers.65 Outboard Inboard 3-D edge transport code : EMC3-EIRENE Impurity screening in stochastic region by friction with bulk plasma flow Retention of impurities via short flux tube in edge surface layer Remarkable reduction of impurity contamination in high density operation CIII/ne exp. CV/ne exp. CIII /ne Sim. CV /ne Sim _ ne (1 m ) (Wed) EX/P4-26 by Burhenn, TH/P4-4 by Feng, (Fri) EX/9-4 by Kobayashi 8 Emission Sim. (1-19 W m3) Inboard Emission Exp. (a.u.).6 Stochastic region 13/17

14 Control of heat load on divertor plate is a major key for steady state operation Critical PRF=.65 MW : Penetration of metal impurities from deposited layer on divertor plate can be simulated by small Fe pellet 2 Te (kev) PRF (MW) ne Divertor Temp. (K) pl Tdiv (K) (119 m-3) before replacing 4 Pulse length (s) 1 τ =-τ log(1-p 3 1 ht RFcr /P ) RF Before After after replacing Time (sec) Averaged RF Power (MW) Divertor plates with significant temperature increase replaced by ones with better heat conductivity critical PRF is mitigated Mode-conversion heating to avoid the production of energetic ions (Thu) EX/P6-29 by Kumazawa 14/17

15 Nearest Future Plan 1. Upgrade of heating capability NBI ICH ECH 5th beam line 7 MW, 6 kev 3 MW steady state 1 MW steady state 2. Closed helical divertor 3. Deuterium Identification and documentation of isotope effect Upgrade of NBI (32 MW in total) 4. Reactor design study FFHR : Force-Free Helical Reactor 15/17

16 Summary 1. High ion temperature 6.8 kev at ne = 2 119m-3 with confinement improvement similar to ITB 2. High beta <β> = 5 %, <β> > 4.5 % for > 1τE 3. High density ne () = m-3 at B = 2.5 T with Internal Diffusion Barrier (IDB) 4. Steady state 1MW for 8 s 5. Near-term upgrade package closed helical divertor, heating capability, deuterium 6. 3-D effect inspiring new advanced physics model and theory which are to be validated in LHD experiment 16/17

17 Contributions from LHD Ion Transport (ITB) EX/8-2Ra (K.Nagaoka), Rb (K.Ida), EX/P5-1 (M.Yoshinuma) High β / MHD EX/8-1Rb (S. Ohdachi), TH/P3-9 (Y.Todo), EX/P5-9 (A.Weller), EX/P8-4 (K.Toi), TH/P9-19 (Y.Suzuki) High Density (IDB) EX/8-1Ra (R.Sakamoto), EX/9-4 (M.Kobayashi), EX/P4-26 (R.Burhenn) Steady State EX/P6-29 (R.Kumazawa) Transport MHD Stability Fast Ion & AE Heating physics Divertor PSI & Dust Reactor TH/6-1 (S.Toda), EX/P5-6 (K.Tanaka), EX/P5-1 (S.Inagaki), EX/P5-11 (T.Fukuda), EX/P6-2 (Y.Nakamura), TH/P8-2 (T.H.Watanabe) TH/P9-16 (H.Miura), TH/P9-17 (N.Mizuguchi), TH/P9-18 (M.Sato) EX/P8-3 (S.Murakami), EX/P8-5 (M.Nishiura) EX/P6-13 (H.Igami), EX/P6-14 (S.Kubo), EX/P6-3 (H.Kasahara) EX/P4-24 (S.Masuzaki), TH/P4-4 (Y.Feng) FT/2-1 (N.Yoshida), EX/P4-7 (N.Ashikawa), EX/P4-8 (T.Hino) FT/P3-17 (S.Imagawa), FT/P3-18 (K.Kozaki), FT/P3-19 (O.Mitarai) 17/17

Recent 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 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 information

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD

Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Akio KOMORI and LHD experiment group National Institute for Fusion Science, Toki, Gifu 509-5292, Japan (Received 4 January 2010 / Accepted

More information

Design window analysis of LHD-type Heliotron DEMO reactors

Design window analysis of LHD-type Heliotron DEMO reactors Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya

More information

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak M. Garcia-Munoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,

More information

Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements

Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements Impact of Energetic-Ion-Driven Global Modes on Toroidal Plasma Confinements Kazuo TOI CHS & LHD Experimental Group National Institute for Fusion Science Toki 59-5292, Japan Special contributions from:

More information

Plasma and Fusion Research: Regular Articles Volume 10, (2015)

Plasma and Fusion Research: Regular Articles Volume 10, (2015) Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE

More information

Tokamak/Helical Configurations Related to LHD and CHS-qa

Tokamak/Helical Configurations Related to LHD and CHS-qa 9TH WORKSHOP ON MHD STABILITY CONTROL: "CONTROL OF MHD STABILITY: BACK TO THE BASICS" NOVEMBER 21-23, 2004, PRINCETON PLASMA PHYSICS LABORATORY Tokamak/Helical Configurations Related to LHD and CHS-qa

More information

US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD.

US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD. US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March 5-7 28 at UCSD. Overview Overview of of Design Design Integration Integration toward toward Optimization -type

More information

Recent Fusion Research in the National Institute for Fusion Science )

Recent Fusion Research in the National Institute for Fusion Science ) Recent Fusion Research in the National Institute for Fusion Science ) Akio KOMORI, Satoru SAKAKIBARA, Akio SAGARA, Ritoku HORIUCHI, Hiroshi YAMADA, Yasuhiko TAKEIRI and NIFS Team National Institute for

More information

Introduction to Fusion Physics

Introduction to Fusion Physics Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction

More information

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén Current density modelling in JET and JT-60U identity plasma experiments Paula Sirén 1/12 1/16 Euratom-TEKES Euratom-Tekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET

More information

Innovative fabrication method of superconducting magnets using high T c superconductors with joints

Innovative fabrication method of superconducting magnets using high T c superconductors with joints Innovative fabrication method of superconducting magnets using high T c superconductors with joints (for huge and/or complicated coils) Nagato YANAGI LHD & FFHR Group National Institute for Fusion Science,

More information

1 EX/P5-9 International Stellarator/Heliotron Database Activities on High-Beta Confinement and Operational Boundaries

1 EX/P5-9 International Stellarator/Heliotron Database Activities on High-Beta Confinement and Operational Boundaries 1 International Stellarator/Heliotron Database Activities on High-Beta Confinement and Operational Boundaries A. Weller 1), K.Y. Watanabe 2), S. Sakakibara 2), A. Dinklage 1), H. Funaba 2), J. Geiger 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

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

Significance of MHD Effects in Stellarator Confinement

Significance of MHD Effects in Stellarator Confinement Significance of MHD Effects in Stellarator Confinement A. Weller 1, S. Sakakibara 2, K.Y. Watanabe 2, K. Toi 2, J. Geiger 1, M.C. Zarnstorff 3, S.R. Hudson 3, A. Reiman 3, A. Werner 1, C. Nührenberg 1,

More information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct 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 US-EU Transport Task Force Annual

More information

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION ASDEX Upgrade Session: "Issues and prospects of effcient fueling for magnetic confinement" HFS ELLET REFUELING FOR HIGH DENSITY TOKAMAK OERATION.T. Lang for the ASDEX Upgrade and JET teams Cubic mm size

More information

The performance of improved H-modes at ASDEX Upgrade and projection to ITER

The performance of improved H-modes at ASDEX Upgrade and projection to ITER EX/1-1 The performance of improved H-modes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOM-Association, D-85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy

More information

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak

Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIII-D Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General

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

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany

Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany DEPTH PROFILE REONSTRUTION FROM RUTHERFORD BAKSATTERING DATA U. V. TOUSSAINT, K. KRIEGER, R. FISHER, V. DOSE Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D-8574 Garching, Germany

More information

Design Windows and Economic Aspect of Helical Reactor

Design Windows and Economic Aspect of Helical Reactor Design Windows and Economic Aspect of Helical Reactor Y. Kozaki, S. Imagawa, A. Sagara National Institute for Fusion Science, Toki, Japan Japan-US Workshop, Kashiwa, March 16-18,2009 - Background and Objectives

More information

D- 3 He HA tokamak device for experiments and power generations

D- 3 He HA tokamak device for experiments and power generations D- He HA tokamak device for experiments and power generations US-Japan Fusion Power Plant Studies Contents University of Tokyo, Japan January -, 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,

More information

Confinement Studies during LHCD and LHW Ion Heating on HL-1M

Confinement Studies during LHCD and LHW Ion Heating on HL-1M Confinement Studies during LHCD and LHW Ion Heating on HL-1M Y. Liu, X.D.Li, E.Y. Wang, J. Rao, Y. Yuan, H. Xia, W.M. Xuan, S.W. Xue, X.T. Ding, G.C Guo, S.K. Yang, J.L. Luo, G.Y Liu, J.E. Zeng, L.F. Xie,

More information

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod

Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod Active and Fast Particle Driven Alfvén Eigenmodes in Alcator C-Mod JUST DID IT. J A Snipes, N Basse, C Boswell, E Edlund, A Fasoli #, N N Gorelenkov, R S Granetz, L Lin, Y Lin, R Parker, M Porkolab, J

More information

Temperature measurement and real-time validation

Temperature measurement and real-time validation Temperature measurement and real-time validation A. Herrmann, B. Sieglin, M. Faitsch, P. de Marné, ASDEX Upgrade team st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis ITER-

More information

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison Heat Transport in a Stochastic Magnetic Field John Sarff Physics Dept, UW-Madison CMPD & CMSO Winter School UCLA Jan 5-10, 2009 Magnetic perturbations can destroy the nested-surface topology desired for

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

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment

Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,

More information

Towards Multiscale Gyrokinetic Simulations of ITER-like Plasmas

Towards Multiscale Gyrokinetic Simulations of ITER-like Plasmas Frank Jenko Max-Planck-Institut für Plasmaphysik, Garching Universität Ulm Towards Multiscale Gyrokinetic Simulations of ITER-like Plasmas 23 rd IAEA Fusion Energy Conference 11-16 October 2010, Daejeon,

More information

Magnetic Confinement Fusion-Status and Challenges

Magnetic Confinement Fusion-Status and Challenges Chalmers energy conference 2012 Magnetic Confinement Fusion-Status and Challenges F. Wagner Max-Planck-Institute for Plasma Physics, Greifswald Germany, EURATOM Association RLPAT St. Petersburg Polytechnic

More information

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012 Fusion research is ready for the next

More information

TRANSP Simulations of ITER Plasmas

TRANSP Simulations of ITER Plasmas PPPL-3152 - Preprint Date: December 1995, UC-420, 421, 427 TRANSP Simulations of ITER Plasmas R. V. Budny, D. C. McCune, M. H. Redi, J. Schivell, and R. M. Wieland Princeton University Plasma Physics Laboratory

More information

Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices

Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices Summary of Thick Liquid FW/Blanket for High Power Density Fusion Devices The replacement of the first wall with a flowing thick liquid offers the advantages of high power density, high reliability and

More information

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO

DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO 21 st IAEA Fusion Energy Conference Chengdu, China Oct. 16-21, 2006 DEPENDENCE OF THE H-MODE PEDESTAL STRUCTURE ON ASPECT RATIO R. Maingi 1, A. Kirk 2, T. Osborne 3, P. Snyder 3, S. Saarelma 2, R. Scannell

More information

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER A. Loarte ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex, France

More information

Reduction 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 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 information

Estimating the plasma flow in a recombining plasma from

Estimating the plasma flow in a recombining plasma from Paper P3-38 Estimating the plasma flow in a recombining plasma from the H α emission U. Wenzel a, M. Goto b a Max-Planck-Institut für Plasmaphysik (IPP) b National Institute for Fusion Science, Toki 509-5292,

More information

Physics of the detached radiative divertor regime in DIII-D

Physics of the detached radiative divertor regime in DIII-D Plasma Phys. Control. Fusion 41 (1999) A345 A355. Printed in the UK PII: S741-3335(99)97299-8 Physics of the detached radiative divertor regime in DIII-D M E Fenstermacher, J Boedo, R C Isler, A W Leonard,

More information

Tokamak Fusion Basics and the MHD Equations

Tokamak Fusion Basics and the MHD Equations MHD Simulations for Fusion Applications Lecture 1 Tokamak Fusion Basics and the MHD Equations Stephen C. Jardin Princeton Plasma Physics Laboratory CEMRACS 1 Marseille, France July 19, 21 1 Fusion Powers

More information

Plasma instability during ITBs formation with pellet injection in tokamak

Plasma instability during ITBs formation with pellet injection in tokamak Plasma instability during ITBs formation with pellet injection in tokamak P. Klaywittaphat 1, B. Chatthong 2, T. Onjun. R. Picha 3, J. Promping 3 1 Faculty of Engineering, Thaksin University, Phatthalung,

More information

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod 1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.

More information

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

MHD instability driven by supra-thermal electrons in TJ-II stellarator

MHD instability driven by supra-thermal electrons in TJ-II stellarator MHD instability driven by supra-thermal electrons in TJ-II stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. Jiménez-Gómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov

More information

Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas

Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas Variation of Turbulence and Transport with the Te/Ti Ratio in H-Mode Plasmas by G.R. McKee with C.H. Holland, C.C. Petty, H. Reimerdes,5, T.R. Rhodes6,L. Schmitz6, S. Smith, I.U. Uzun-Kaymak, G. Wang6,

More information

Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles

Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles Y. Hirohata 1), T. Tanabe 2), Y. Oya 3), K. Shibahara 4), M. Oyaidzu 5), T. Arai 6), K. Masaki 6), Y. Gotoh 6), K. Okuno

More information

EFDA European Fusion Development Agreement - Close Support Unit - Garching

EFDA European Fusion Development Agreement - Close Support Unit - Garching Multi-machine Modelling of Divertor Geometry Effects Alberto Loarte EFDA CSU -Garching Acknowledgements: K. Borrass, D. Coster, J. Gafert, C. Maggi, R. Monk, L. Horton, R.Schneider (IPP), A.Kukushkin (ITER),

More information

Nuclear Fusion and ITER

Nuclear Fusion and ITER Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development

More information

L-to-H power threshold comparisons between NBI and RF heated plasmas in NSTX

L-to-H power threshold comparisons between NBI and RF heated plasmas in NSTX Research Supported by L-to-H power threshold comparisons between NBI and RF heated plasmas in NSTX T.M. Biewer 1, R. Maingi 1, H. Meyer 2, R.E. Bell 3, C. Bush 1, S. Kaye 3, S. Kubota 3, B. LeBlanc 3,

More information

Gyrokinetic Transport Driven by Energetic Particle Modes

Gyrokinetic Transport Driven by Energetic Particle Modes Gyrokinetic Transport Driven by Energetic Particle Modes by Eric Bass (General Atomics) Collaborators: Ron Waltz, Ming Chu GSEP Workshop General Atomics August 10, 2009 Outline I. Background Alfvén (TAE/EPM)

More information

The Advanced Tokamak: Goals, prospects and research opportunities

The Advanced Tokamak: Goals, prospects and research opportunities The Advanced Tokamak: Goals, prospects and research opportunities Amanda Hubbard MIT Plasma Science and Fusion Center with thanks to many contributors, including A. Garafolo, C. Greenfield, C. Kessel,

More information

Steady-state operation scenario and the first experimental result on QUEST

Steady-state operation scenario and the first experimental result on QUEST Steady-state operation scenario and the first experimental result on QUEST K.Hanada 1), K.N.Sato 1), H.Zushi 1), K.Nakamura 1), M.Sakamoto 1), H.Idei 1), M.Hasegawa 1), Y.Takase 2), O.Mitarai 3), T.Maekawa

More information

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT

PFC/JA NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT PFC/JA-88-12 NEUTRAL BEAM PENETRATION CONSIDERATIONS FOR CIT J. Wei, L. Bromberg, R. C. Myer, and D. R. Cohn Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 2139 To

More information

Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna, Austria Sept. 1-4, 2015

Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna, Austria Sept. 1-4, 2015 Review of Theory Papers at 14 th IAEA technical meeting on Engertic Particles in Magnetic Confinement systems Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna,

More information

Fusion Nuclear Science (FNS) Mission & High Priority Research

Fusion Nuclear Science (FNS) Mission & High Priority Research Fusion Nuclear Science (FNS) Mission & High Priority Research Topics Martin Peng, Aaron Sontag, Steffi Diem, John Canik, HM Park, M. Murakami, PJ Fogarty, Mike Cole ORNL 15 th International Spherical Torus

More information

Rotation and Neoclassical Ripple Transport in ITER

Rotation 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 information

Progress in characterization of the H-mode pedestal

Progress in characterization of the H-mode pedestal Journal of Physics: Conference Series Progress in characterization of the H-mode pedestal To cite this article: A W Leonard 2008 J. Phys.: Conf. Ser. 123 012001 View the article online for updates and

More information

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE 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 information

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER M.L. Reinke 1, A. Loarte 2, M. Chilenski 3, N. Howard 3, F. Köchl 4, A. Polevoi 2, A. Hubbard 3, J.W. Hughes

More information

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared

More information

q(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5

q(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5 EX/P-1 MHD issues in Tore Supra steady-state fully non-inductive scenario P Maget 1), F Imbeaux 1), G Giruzzi 1), V S Udintsev ), G T A Huysmans 1), H Lütjens 3), J-L Ségui 1), M Goniche 1), Ph Moreau

More information

CATHODE MATERIAL CHANGE AFTER DEUTERIUM GLOW DISCHARGE EXPERIMENTS

CATHODE MATERIAL CHANGE AFTER DEUTERIUM GLOW DISCHARGE EXPERIMENTS Savvatimova, I., Y. Kucherov, and A.B. Karabut. Cathode Material Change after Deuterium Glow Discharge Experiments. in Fourth International Conference on Cold Fusion. 1993. Lahaina, Maui: Electric Power

More information

Stability Properties of Toroidal Alfvén Modes Driven. N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye

Stability Properties of Toroidal Alfvén Modes Driven. N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye Stability Properties of Toroidal Alfvén Modes Driven by Fast Particles Λ N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton,

More information

Fusion Nuclear Science - Pathway Assessment

Fusion Nuclear Science - Pathway Assessment Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,

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

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Neutron and gamma ray measurements. for fusion experiments and spallation sources

Neutron and gamma ray measurements. for fusion experiments and spallation sources Neutron and gamma ray measurements for fusion experiments and spallation sources Carlo Cazzaniga prof.ssa Claudia Riccardi 1 External supervisor: dr. Marco Tardocchi Supervisor: 1) Istituto di Fisica del

More information

The Physics Basis of ITER Confinement

The Physics Basis of ITER Confinement The Physics Basis of ITER Confinement F. Wagner Max-Planck-Institut für Plasmaphysik EURATOM Association Wendelsteinstr. 1, 17491 Greifswald, Germany Abstract. ITER will be the first fusion reactor and

More information

Plasma Spectroscopy Inferences from Line Emission

Plasma 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 information

ICRH Experiments on the Spherical Tokamak Globus-M

ICRH Experiments on the Spherical Tokamak Globus-M 1 Experiments on the Spherical Tokamak Globus-M V.K.Gusev 1), F.V.Chernyshev 1), V.V.Dyachenko 1), Yu.V.Petrov 1), N.V.Sakharov 1), O.N.Shcherbinin 1), V.L.Vdovin 2) 1) A.F.Ioffe Physico-Technical Institute,

More information

Reinstallation of the COMPASS D Tokamak in IPP ASCR

Reinstallation of the COMPASS D Tokamak in IPP ASCR R. Pánek, O. Bilyková, V. Fuchs, M. Hron, P. Chráska, P. Pavlo, J. Stöckel, J. Urban, V. Weinzettl, J. Zajac and F. Žáček Institute of Plasma Physics, Academy of Sciences of the Czech Republic, Za Slovankou

More information

Evolution of the pedestal on MAST and the implications for ELM power loadings

Evolution of the pedestal on MAST and the implications for ELM power loadings Evolution of the pedestal on MAST and the implications for ELM power loadings Presented by Andrew Kirk EURATOM / UKAEA Fusion Association UKAEA authors were funded jointly by the United Kingdom Engineering

More information

Chapter 12. Magnetic Fusion Toroidal Machines: Principles, results, perspective

Chapter 12. Magnetic Fusion Toroidal Machines: Principles, results, perspective Chapter 12 Magnetic Fusion Toroidal Machines: Principles, results, perspective S. Atzeni May 10, 2010; rev.: May 16, 2012 English version: May 17, 2017 1 Magnetic confinement fusion plasmas low density

More information

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod PFC/JA-94-15 Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod J.A. Goetz, B. Lipschultz, M.A. Graf, C. Kurz, R. Nachtrieb, J.A. Snipes, J.L. Terry Plasma

More information

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team*

QTYUIOP ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL. Presented by. for the DIII D Team* ENERGY TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR Presented by D.P. SCHISSEL for the DIII D Team* Presented to 38th APS/DPP Meeting NOVEMBER 11 15, 1996 Denver, Colorado

More information

J. Kesner. April Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts USA

J. Kesner. April Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts USA PFC/JA-88-38 Effect of Local Shear on Drift Fluctuation Driven T'ransport in Tokamaks J. Kesner April 1989 Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 2139 USA Submitted

More information

Q, Break-even and the nτ E Diagram for Transient Fusion Plasmas

Q, Break-even and the nτ E Diagram for Transient Fusion Plasmas Q, Break-even and the nτ E Diagram for Transient Plasmas Dale M. Meade Princeton University P.O. Box 451, Princeton, N. J. 08543 Abstract - Q, break-even and the nτe diagram are well defined and understood

More information

Observation of Alpha Heating in JET DT Plasmas

Observation of Alpha Heating in JET DT Plasmas JET P(98)1 Observation of Alpha Heating in JET DT Plasmas P R Thomas, P Andrew, B Balet, D Bartlett, J Bull, B de Esch, C Gowers, H Guo, G Huysmans, T Jones, M Keilhacker, R König, M Lennholm, P Lomas,

More information

Effects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal

Effects 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 information

Simulations of H-Mode Plasmas in Tokamak Using a Complete Core-Edge Modeling in the BALDUR Code

Simulations of H-Mode Plasmas in Tokamak Using a Complete Core-Edge Modeling in the BALDUR Code Plasma Science and Technology, Vol.14, No.9, Sep. 2012 Simulations of H-Mode Plasmas in Tokamak Using a Complete Core-Edge Modeling in the BALDUR Code Y. PIANROJ, T. ONJUN School of Manufacturing Systems

More information

Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of. ASDEX Upgrade

Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of. ASDEX Upgrade Association Euratom-Tekes ASDEX Upgrade Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of ASDEX Upgrade L. Aho-Mantila 1,2, M. Wischmeier 3, K. Krieger 3, V. Rohde 3,

More information

INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS

INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS A.D. Turnbull and L.L. Lao General Atomics (with contributions from W.A. Cooper and R.G. Storer) Presentation

More information

Plasma heating with neutral beam injection

Plasma heating with neutral beam injection University in Ljubljana Faculty of mathematics and physics Department of physics Plasma heating with neutral beam injection SEMINAR Author: Jure Maglica Mentor: a/prof. dr. Milan Čerček Ljubljana, May

More information

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor J.N. Brooks, J.P. Allain Purdue University PFC Meeting MIT, July 8-10, 2009 CMOD Mo tile divertor erosion/redeposition

More information

Physics fundamentals for ITER

Physics fundamentals for ITER Plasma Phys. Control. Fusion 41 (1999) A99 A113. Printed in the UK PII: S0741-3335(99)97512-7 Physics fundamentals for ITER ITER-JCT, ITER San Diego Joint Work Site, 11025 North Torrey Pines Rd, La Jolla,

More information

The New Sorgentina Fusion Source Project

The New Sorgentina Fusion Source Project The New Sorgentina Fusion Source Project P. Agostini, P. Console Camprini, D. Bernardi, M. Pillon, M. Frisoni, M. Angelone, A. Pietropaolo, P. Batistoni, A. Pizzuto ENEA Agenzia Nazionale per le Nuove

More information

PROBLEM SET. Heliophysics Summer School. July, 2013

PROBLEM SET. Heliophysics Summer School. July, 2013 PROBLEM SET Heliophysics Summer School July, 2013 Problem Set for Shocks and Particle Acceleration There is probably only time to attempt one or two of these questions. In the tutorial session discussion

More information

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

On Heat Loading, Novel Divertors, and Fusion Reactors. Abstract

On Heat Loading, Novel Divertors, and Fusion Reactors. Abstract On Heat Loading, Novel Divertors, and Fusion Reactors M. Kotschenreuther, P. M. Valanju, and S. M. Mahajan Institute for Fusion Studies, The University of Texas at Austin (Dated: March 22, 2006) Abstract

More information

The role of PMI in MFE/IFE common research

The role of PMI in MFE/IFE common research The role of PMI in MFE/IFE common research Presented by Doerner for the Team and TITAN 1-1 Participants In 2006, Jupiter II recognized that PMI was a bridge issue between MFE and IFE R&D Both MFE and IFE

More information

Modelling of the penetration process of externally applied helical magnetic perturbation of the DED on the TEXTOR tokamak

Modelling of the penetration process of externally applied helical magnetic perturbation of the DED on the TEXTOR tokamak INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 8 (6) 69 8 PLASMA PHYSICS AND CONTROLLED FUSION doi:.88/7-/8// Modelling of the penetration process of externally applied helical magnetic perturbation

More information

Enhanced con nement discharges in DIII-D with neon and argon induced radiation

Enhanced con nement discharges in DIII-D with neon and argon induced radiation Journal of Nuclear Materials 266±269 (1999) 380±385 Enhanced con nement discharges in DIII-D with neon and argon induced radiation G.L. Jackson a, *, M. Murakami b, G.M. Staebler a, M.R. Wade b, A.M. Messiaen

More information

Progress Towards Burning Plasmas )

Progress Towards Burning Plasmas ) Progress Towards Burning Plasmas ) James W. VAN DAM 1,2) 1) U.S. Burning Plasma Organization & U.S. ITER Project Office 2) Institute for Fusion Studies, The University of Texas at Austin, Austin, Texas

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

The role of zonal flows and predator-prey oscillations in triggering

The role of zonal flows and predator-prey oscillations in triggering The role of zonal flows and predator-prey oscillations in triggering the formation of edge and core transport barriers L. Schmitz, 1 L. Zeng, 1 T.L. Rhodes, 1 J.C. Hillesheim 2 W.A. Peebles, 1 R.J. Groebner,

More information

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012

W.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29-November 2, 2012 Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty

More information

Gyrokinetic Turbulence Simulations at High Plasma Beta

Gyrokinetic Turbulence Simulations at High Plasma Beta Gyrokinetic Turbulence Simulations at High Plasma Beta Moritz J. Pueschel Thanks to F. Jenko and M. Kammerer Ringberg Theory Meeting, Nov. 18, 2008 1 Motivation 2 3 The Beta Parameter Definition β β e

More information

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT GA A3736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT by T.C. LUCE, C.C. PETTY, and J.E. KINSEY AUGUST DISCLAIMER This report was prepared as an account of work sponsored by an

More information

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME by R. NAZIKIAN, M.E. AUSTIN, R.V. BUDNY, M.S. CHU, W.W. HEIDBRINK, M.A. MAKOWSKI, C.C. PETTY, P.A. POLITZER, W.M. SOLOMON, M.A.

More information