Modeling of Transport Barrier Based on Drift Alfvén Ballooning Mode Transport Model

Size: px
Start display at page:

Download "Modeling of Transport Barrier Based on Drift Alfvén Ballooning Mode Transport Model"

Transcription

1 9th IAEA TM on H-mode Physics and Transport Barriers Catamaran Resort Hotel, San Diego Modeling of Transport Barrier Based on Drift Alfvén Ballooning Mode Transport Model A. Fukuyama, M. Uchida and M. Honda Department of Nuclear Engineering, Kyoto University, Kyoto 66-85, Japan

2 Motivation Development of Robust Transport Model L-mode confinement time scaling Large transport near the plasma edge in L-mode H-mode confinement time scaling for given edge temperature Formation of internal transport barrier Profile database (ITPA) Behavior of fluctuation Purpose of the present model To describe both Electrostatic ITG mode enhanced transport for large ion temperature gradient Electromagnetic Ballooning mode (CDBM) transport reduction for negative s α: ITB formation magnetic shear: s = r q dq dr pressure gradient (Shafranov shift): α = q R dβ dr

3 Turbulent Transport Model CDBM Reduced MHD equation Electromagnetic Incompressible Toroidal ITG[h Ion Fluid Equation Electrostatic Boltzmann Distribution of Electron Drift Alfvén Ballooning Mode Reduced Two-Fluid Equation Electromagnetic Compressible Small pressure gradient: Electrostatic ITG Large pressure gradient: Electromagnetic BM Without drift motion, it reduces to CDBM Ion parallel viscosity and compressibility destabilizes the mode s α dependence similar to the CDBM mode

4 Reduced Two-Fluid Equation (Slab Plasma) Equation of Vorticity [ ni Λ ɛ Ω i B e n ] eλ e φ Ω e B t (n i v i n e v e ) + = eb ( b κ + b B ) B + n i Ω i B t ( ieni Λ i ω i T i ( ) p i n e q i n i Ω e B ) + ien eλ e ω e T e ( p i + p e ) Parallel Equation of Motion (j = e, i) v j m j n j + p j q j n j E = t Equation of State (j = e, i) p j t + v E p j + Γ j p j v j = Ampere s Law A = µ (n q j v j ) j φ t ( ) p e q e n e

5 Linear Analysis: Slab Plasma Slab ITG mode (Comparison of three models) Ion Fluid Model (3 eqs.) Reduced Two-Fluid Model (6 eqs.) Full Two-Fluid Model (4 eqs.) γ/ω e γ/ω *e ω r /ω e 3 3 equations(φ,v,p i ) 6 equations (φ,v j,p j,a ) 4 equations (φ,n j,v jx,v jy, v jz,p j,a) 4..4 k y ρ i 4 η e ω r /ω *e 4 equations (η i =5) 4 equations (η i =3) 4 equations (η i =) 6 equations (η i =5) Reduced two-fluid model is very close to the full two-fluid model.

6 Reduced Two-Fluid Equation (Toroidal Plasma) Ballooning transformation: ξ Equation of Vorticity iω Ω i B m r f iωem f φ ɛ r ( n i Λ i φ + p i q i ) iω m ( Ω e B r f n e Λ e φ + p ) e q e + B θ rb ξ (n iv j n e v e ) imb ϕ err B H(ξ)(p i + p e ) = Parallel Equation of Motion (j = e, i) iωm j n j v j + B ( θ p rb ξ + q Bθ Λ j jn j rb Equation of State (j = e, i) ) φ ξ iω aja = Ampere s law iωp j iq j n j Λ j ω j ( + η j )φ + Γ jp j B θ rb v j ξ = m r f A = µ e(n i v i n e v e ) H(ξ) κ + cos ξ + (sξ α sin ξ) sin ξ, f (ξ) = + (sξ α sin ξ)

7 Linear Analysis: Toroidal Plasma Ballooning mode (Transition from electrostatic to electromagnetic) Electrostatic Toroidal ITG Mode Electromagnetic Ballooning Mode α.5 ω r /ω *e.6 γ/ω *e γ/ω *e Eelectro Magnetic ω r /ω *e γ/ω *e. Ballooning Mode α=.8 α=.3 α=.8.5 α=.8 α=.3 α=.8.4 Eelectro Static ITG Mode ω r /ω *e..4.6 k ρ i..4.6 k ρ i 5 η j Electromagnetic effect becomes dominant for large η i or α

8 Nonlinear Reduced Two-Fluid Equation (Toroidal Plasma) Turbulent transport coefficients are included. d φ dt X j iωx j χ j X j, χ j = γ nj φ Equation of Vorticity: m [( iω f + µ i ) n i iωe m f ( iω + µ r e ) n ] e m f φ Ω i B ɛ r Ω e B r m + ( iω f ) m + χ i r Ω i B r f p i m ( iω f ) m + χ e q i r Ω e B r f p e q e + B θ rb ξ (n iv j n e v e ) imb ϕ err B H(ξ)(p i + p e ) = Parallel Equation of Motion ( m f ) m j n j iω + µ j v r j + B θ p rb ξ + q jn j Equation of State m ( iω f ) + χ j r ( Bθ Λ j rb p j iq j n j Λ j ω j ( + η j )φ + Γ jp j B θ rb ) φ ξ iω aja v j ξ = =

9 Ampere s Law m r f A = µ e(n i v i n e v e ) CDBM Eigenmode Equation ξ γf γ + η r m f + λm 4 f φ ξ (γ f + γµm f)φ + Marginal Stability Condition (γ = ) φ λ ξ µm6 f 3 φ + αm f χ H(ξ)φ = αγ γ + χm f H(ξ)φ = Low β DABM Eigenmode Equation: Marginal Stability Condition φ ξ µ τap iχ c m 6 f 3 i r 6 ωpi φ + m c α i r ωpi H(ξ)φ = Eigenmode equations for CDBM and DABM are similar.

10 Nonlinear Analysis (Toroidal Plasma) Amplitude Dependence of the Growth Rate Linear growth rate (χ j = ) is sensitive to k ρ i. For large α, electromagnetic effect becomes important. Saturation level can be estimated from the marginal condition..8 (α=., s=.4, k ρ i =.6) (a) (α=., s=.4, k ρ i =.36) (b) ITGM (α=., s=.4, k ρ i =.) (c) γ/ω *e.6.4 γ/ω *e. γ/ω *e.4 DABM.. χ j, µ j [m /s] µ j, χ j [m /s] µ j, χ j [m /s]

11 Dependence on s and α Transport of DABM is much larger than that of CDBM. Negative magnetic shear reduces the transport. χ is proportional to α 3/ for small α. There exists critical α above which transport is strongly enhanced. [m /s] (α=.) χ j, µ j χ j ω r /ω *e 3 s DABM CDBM s=.8 s=.4 s=. s=.4(em) s=.4(es) α s=.8 s=.4 s=. s=.4 s=.4 α

12 Contour of χ on s-α plane s µ j, χ j [m /s] s µ j, χ j [m /s] Uncertain (nq<) α α CDBM DABM

13 DABM Turbulence Model Low β DABM Eigenmode Equation: (γ = ) φ ξ µ τap iχ c m 6 f 3 i r 6 ωpi φ + m c α i r ωpi H(ξ)φ = Marginal Stability Condition χ DABM = F (s, α, κ) α c ω pe v Te qr.5. s α dependence of F (s, α, κ, ω E ) ω E = ω E =. Magnetic shear Pressure gradient Magnetic curvature κ r R s r dq q dr α q R dβ dr ( ) q Different gradient dependence with CDBM Weak and negative magnetic shear and Shafranov shift reduce χ. F F = ω E =. ω E = s - α Fitting Formula + G ωe ( s )( s + 3s ) for s = s α < + 9 s 5/ + G ωe ( s + 3s + s 3 ) for s = s α >

14 High β p mode Empirical factor of 3 was chosen to reproduce the L-mode scaling. R = 3 m, a =. m, κ =.5, B = 3 T, I p =.5 MA Time evolution during the first one second after MW heating switched on. Temperature evolution Temperature Safety factor TE,TD,<TE>,<TD> [kev] vs t 4 3 T D T e <T D > <T e > TD [kev] vs r T D QP vs r q Current evolution Current density Thermal diffusivity IP,IOH,INB,IRF,IBS [MA] vs t I BS I OH I tot JTOT,JOH,JNB,JRF,JBS [MA/m^] vs r J OH J BS J tot AKD [m^/s] vs r 4 3 χ i

15 Summary In order to describe both the electrostatic ion temperature gradient (ITG) mode and the electromagnetic current diffusive ballooning mode (CDBM), we have derived a set of reduced two-fluid equations in both slab and toroidal configurations and numerically solved them as an eigenvalue problem. Linear analysis in a toroidal configuration describes a ballooning mode, which we call DABM (Drift Alfvén Ballooning Mode). Small pressure gradient: Toroidal ITG mode Large pressure gradient: Ballooning mode with stabilizing ω Based on the theory of self-sustained turbulence, we have numerically calculated the transport coefficients from the marginal stability condition. When α is small, χ is approximately proportional to α 3/. χ is an increasing function of s α; similar to CDBM model which successfully reproduces the ITB formation.

16 When α exceeds a critical value, χ starts to increase strongly with α, which may suggest the stiffness of the profile Using an electrostatic approximation, we have derived a formula of thermal diffusivity slightly different from the CDBM model. Preliminary transport simulation reproduces the formation of ITB. The barrier locates in outer region and the gradient is steeper than the CDBM model. More general expression is required for high-β electromagnetic region.

17 CDBM Turbulence Model Marginal Stability Condition (γ = ) χ CDBM = F (s, α, κ, ω E ) α 3/ Magnetic shear Pressure gradient Magnetic curvature c ω pe v A qr s r dq q dr α q R dβ dr κ r ( ) R q E B rotation shear ω E r sv A d dr Weak and negative magnetic shear, Shafranov shift and E B rotation shear E rb reduce thermal diffusivity. F F = s α dependence of F (s, α, κ, ω E ) ω E = ω E =. ω E =. ω E = s - α Fitting Formula + G ωe ( s )( s + 3s ) for s = s α < + 9 s 5/ + G ωe ( s + 3s + s 3 ) for s = s α >

18 Heat Transport Simulation Simple One-Dimensional Analysis No impurity, No neutral, No sawtooth Fixed density profile: n e (r) ( r /a ) / Thermal diffusivity (adjustable parameter C = ) Transport Equation t t 3 n et e = r 3 n it i = r χ e = Cχ TB + χ NC,e χ i = Cχ TB + χ NC,i r r n eχ e T e r + P OH + P ie + P He r r n iχ i T i r P ie + P Hi t B θ = [ r η NC µ r r rb θ J BS J LH Standard Plasma Parameter R = 3 m B t = 3 T Elongation =.5 a =. m I p = 3 MA n e = 5 9 m 3 ]

19 High β p mode () R = 3 m, a =. m, κ =.5, B = 3 T, I p = MA Time evolution during the first one second after heating switched on Temperater Current Safety factor T [kev] 6 4 T e J [MA/m ].6.4. J TOT q 8 4 q Shear Normalized Pressure Thermal diffusivity s s α 4 3 α χ [m /s] 5 5 χ D

20 High β p mode () One second after heating power of P H = MW was switched on Temperater profile Current profile Safety factor T [kev] 6 4 T D T e J [MA/m ] J TOT J BS J OH q 8 4 q Shear and pressure Thermal diffusivity s α diagram s, α, F(s,α) 4 3 α F(s,α) s χ [m /s] 5 χ D 5 χ TB χ NC s r=.m.6 s after heating on. before heating.8 r=.6m r=.6m.4 r=m α

21 Simulation of Current Hole Formation Current ramp up: I p =.5. MA Moderate heating: P H = 5 MW Current hole is formed. The formation is sensitive to the edge temperature.

22 Simulation of Reversed Shear Configuration I p : 3 MA constant Heating : MW H factor.95 I p : MA 3 MA/ s Heating : MW H factor.6 I [MA] I OH I BS I [MA] I p I BS I OH T [kev] T e <T e > <T D > T D T [kev] T e T D <T e > <T D > τ E [s] τ E τ E ITER89 τ E [s] τ E τ E ITER89 t [s] t [s]

23 Evolution of Reversed Shear Configuration I p : 3 MA constant I p : MA 3 MA/ s j tot (r) j tot (r) j [MA/m ] j [MA/m ] t = 5 s j tot q(r) q(r) j [MA/m ] j OH j BS q q T [kev] T D (r) T [kev] T D (r) χ [m /s ] χ NC χ TB χ D

(a) (b) (0) [kev] 1+Gω E1. T e. r [m] t [s] t = 0.5 s 6.5 MW. t = 0.8 s 5.5 MW 4.5 MW. t = 1.0 s t = 2.0 s

(a) (b) (0) [kev] 1+Gω E1. T e. r [m] t [s] t = 0.5 s 6.5 MW. t = 0.8 s 5.5 MW 4.5 MW. t = 1.0 s t = 2.0 s FORMTION ND COLLPSE OF INTERNL TRNSPORT BRRIER. Fukuyama Department of Nuclear Engineering, Kyoto University, Kyoto K. Itoh National Institute for Fusion Science, Toki, Gifu S.-I. Itoh, M. Yagi Research

More information

Gyrokinetic Theory and Dynamics of the Tokamak Edge

Gyrokinetic Theory and Dynamics of the Tokamak Edge ASDEX Upgrade Gyrokinetic Theory and Dynamics of the Tokamak Edge B. Scott Max Planck Institut für Plasmaphysik D-85748 Garching, Germany PET-15, Sep 2015 these slides: basic processes in the dynamics

More information

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

Role 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 information

Modeling of ELM Dynamics for ITER

Modeling of ELM Dynamics for ITER Modeling of ELM Dynamics for ITER A.Y. PANKIN 1, G. BATEMAN 1, D.P. BRENNAN 2, A.H. KRITZ 1, S. KRUGER 3, P.B. SNYDER 4 and the NIMROD team 1 Lehigh University, 16 Memorial Drive East, Bethlehem, PA 18015

More information

Formation 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 ) 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 311-0102, Japan 1) University

More information

QTYUIOP LOCAL ANALYSIS OF CONFINEMENT AND TRANSPORT IN NEUTRAL BEAM HEATED DIII D DISCHARGES WITH NEGATIVE MAGNETIC SHEAR D.P. SCHISSEL.

QTYUIOP 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 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

Characteristics of the H-mode H and Extrapolation to ITER

Characteristics of the H-mode H and Extrapolation to ITER Characteristics of the H-mode H Pedestal and Extrapolation to ITER The H-mode Pedestal Study Group of the International Tokamak Physics Activity presented by T.Osborne 19th IAEA Fusion Energy Conference

More information

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling

Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling Validation of Theoretical Models of Intrinsic Torque in DIII-D and Projection to ITER by Dimensionless Scaling by B.A. Grierson1, C. Chrystal2, W.X. Wang1, J.A. Boedo3, J.S. degrassie2, W.M. Solomon2,

More information

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions

Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions 7th APTWG Intl. Conference 5-8 June 2017 Nagoya Univ., Nagoya, Japan Andreas Bierwage, Yasushi Todo 14.1MeV 10 kev

More information

Turbulent Transport due to Kinetic Ballooning Modes in High-Beta Toroidal Plasmas

Turbulent Transport due to Kinetic Ballooning Modes in High-Beta Toroidal Plasmas 1 TH/P-3 Turbulent Transport due to Kinetic allooning Modes in High-eta Toroidal Plasmas A. Ishizawa 1, S. Maeyama, T.-H. Watanabe 1, H. Sugama 1 and N. Nakajima 1 1 National Institute for Fusion Science,

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

DIII D UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN DIII D QTYUIOP C.M. GREENFIELD. Presented by

DIII 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 information

THE DIII D PROGRAM THREE-YEAR PLAN

THE DIII D PROGRAM THREE-YEAR PLAN THE PROGRAM THREE-YEAR PLAN by T.S. Taylor Presented to Program Advisory Committee Meeting January 2 21, 2 3 /TST/wj PURPOSE OF TALK Show that the program plan is appropriate to meet the goals and is well-aligned

More information

TURBULENT TRANSPORT THEORY

TURBULENT TRANSPORT THEORY ASDEX Upgrade Max-Planck-Institut für Plasmaphysik TURBULENT TRANSPORT THEORY C. Angioni GYRO, J. Candy and R.E. Waltz, GA The problem of Transport Transport is the physics subject which studies the physical

More information

ENERGETIC PARTICLES AND BURNING PLASMA PHYSICS

ENERGETIC PARTICLES AND BURNING PLASMA PHYSICS ENERGETIC PARTICLES AND BURNING PLASMA PHYSICS Reported by J. Van Dam Institute for Fusion Studies The University of Texas at Austin US-Japan JIFT Workshop on Theory-Based Modeling and Integrated Simulation

More information

High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows

High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows TH/P3-3 High-m Multiple Tearing Modes in Tokamaks: MHD Turbulence Generation, Interaction with the Internal Kink and Sheared Flows A. Bierwage 1), S. Benkadda 2), M. Wakatani 1), S. Hamaguchi 3), Q. Yu

More information

Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry

Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry Comparison of Kinetic and Extended MHD Models for the Ion Temperature Gradient Instability in Slab Geometry D. D. Schnack University of Wisconsin Madison Jianhua Cheng, S. E. Parker University of Colorado

More information

Computational Study of Non-Inductive Current Buildup in Compact DEMO Plant with Slim Center Solenoid

Computational Study of Non-Inductive Current Buildup in Compact DEMO Plant with Slim Center Solenoid 1st IAEA TM, First Generation of Fusion Power Plants Design and Technology -, Vienna, July 5-7, 25 Computational Study of Non-Inductive Current Buildup in Compact DEMO Plant with Slim Center Solenoid Y.

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS 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 information

Tests of Profile Stiffness Using Modulated Electron Cyclotron Heating

Tests of Profile Stiffness Using Modulated Electron Cyclotron Heating Tests of Profile Stiffness Using Modulated Electron Cyclotron Heating by T.C. Luce in collaboration with J.C. DeBoo, C.C. Petty, J. Pino, J.M. Nelson, and J.C.M. dehaas Presented at 9th EU-US Transport

More information

Effects of Alpha Particle Transport Driven by Alfvénic Instabilities on Proposed Burning Plasma Scenarios on ITER

Effects of Alpha Particle Transport Driven by Alfvénic Instabilities on Proposed Burning Plasma Scenarios on ITER Effects of Alpha Particle Transport Driven by Alfvénic Instabilities on Proposed Burning Plasma Scenarios on ITER G. Vlad, S. Briguglio, G. Fogaccia, F. Zonca Associazione Euratom-ENEA sulla Fusione, C.R.

More information

Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters

Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters Time-domain simulation and benchmark of LHCD experiment at ITER relevant parameters S. Shiraiwa, P. Bonoli, F. Poli 1, R. W, Harvey 2, C. Kessel 1, R. Parker, and G. Wallace MIT-PSFC, PPPL 1, and CompX

More information

INTERACTION OF DRIFT WAVE TURBULENCE AND MAGNETIC ISLANDS

INTERACTION OF DRIFT WAVE TURBULENCE AND MAGNETIC ISLANDS INTERACTION OF DRIFT WAVE TURBULENCE AND MAGNETIC ISLANDS A. Ishizawa and N. Nakajima National Institute for Fusion Science F. L. Waelbroeck, R. Fitzpatrick, W. Horton Institute for Fusion Studies, University

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

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

Studies 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 information

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma

Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma 1 Impact of diverted geometry on turbulence and transport barrier formation in 3D global simulations of tokamak edge plasma D. Galassi, P. Tamain, H. Bufferand, C. Baudoin, G. Ciraolo, N. Fedorczak, Ph.

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

Understanding physics issues of relevance to ITER

Understanding physics issues of relevance to ITER Understanding physics issues of relevance to ITER presented by P. Mantica IFP-CNR, Euratom/ENEA-CNR Association, Milano, Italy on behalf of contributors to the EFDA-JET Work Programme Brief summary of

More information

Innovative Concepts Workshop Austin, Texas February 13-15, 2006

Innovative Concepts Workshop Austin, Texas February 13-15, 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 information

Global particle-in-cell simulations of Alfvénic modes

Global particle-in-cell simulations of Alfvénic modes Global particle-in-cell simulations of Alfvénic modes A. Mishchenko, R. Hatzky and A. Könies Max-Planck-Institut für Plasmaphysik, EURATOM-Association, D-749 Greifswald, Germany Rechenzentrum der Max-Planck-Gesellschaft

More information

A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows *

A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows * A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows * Bruce I. Cohen, Maxim V. Umansky, Ilon Joseph Lawrence Livermore National Laboratory

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

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas

Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas Bounce-averaged gyrokinetic simulations of trapped electron turbulence in elongated tokamak plasmas Lei Qi a, Jaemin Kwon a, T. S. Hahm a,b and Sumin Yi a a National Fusion Research Institute (NFRI), Daejeon,

More information

C-Mod Transport Program

C-Mod Transport Program C-Mod Transport Program PAC 2006 Presented by Martin Greenwald MIT Plasma Science & Fusion Center 1/26/2006 Introduction Programmatic Focus Transport is a broad topic so where do we focus? Where C-Mod

More information

Particle-in-cell simulations of electron transport from plasma turbulence: recent progress in gyrokinetic particle simulations of turbulent plasmas

Particle-in-cell simulations of electron transport from plasma turbulence: recent progress in gyrokinetic particle simulations of turbulent plasmas Institute of Physics Publishing Journal of Physics: Conference Series 16 (25 16 24 doi:1.188/1742-6596/16/1/2 SciDAC 25 Particle-in-cell simulations of electron transport from plasma turbulence: recent

More information

ELMs and Constraints on the H-Mode Pedestal:

ELMs and Constraints on the H-Mode Pedestal: ELMs and Constraints on the H-Mode Pedestal: A Model Based on Peeling-Ballooning Modes P.B. Snyder, 1 H.R. Wilson, 2 J.R. Ferron, 1 L.L. Lao, 1 A.W. Leonard, 1 D. Mossessian, 3 M. Murakami, 4 T.H. Osborne,

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

Electron Transport and Improved Confinement on Tore Supra

Electron Transport and Improved Confinement on Tore Supra Electron Transport and Improved Confinement on Tore Supra G. T. Hoang, C. Bourdelle, X. Garbet, T. Aniel, G. Giruzzi, M. Ottaviani. Association EURATOM-CEA. CEA-Cadarache, 38, St Paul-lez-Durance, France

More information

Core and edge toroidal rotation study in JT-60U

Core and edge toroidal rotation study in JT-60U Core and edge toroidal rotation study in JT-6U Japan Atomic Energy Agency M. Yoshida, Y. Sakamoto, M. Honda, Y. Kamada, H. Takenaga, N. Oyama, H. Urano, and the JT-6 team JT-6U EXC/3-2 1 23rd IAEA Fusion

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 A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES

GA 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 information

Nonlinear MHD effects on TAE evolution and TAE bursts

Nonlinear MHD effects on TAE evolution and TAE bursts Nonlinear MHD effects on TAE evolution and TAE bursts Y. Todo (NIFS) collaborating with H. L. Berk and B. N. Breizman (IFS, Univ. Texas) GSEP 3rd Annual Meeting (remote participation / Aug. 9-10, 2010)

More information

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK ITER operation Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 14 th March 2014 Ben Dudson Magnetic Confinement Fusion (1 of 18) ITER Some key statistics for ITER are:

More information

MHD Linear Stability Analysis Using a Full Wave Code

MHD Linear Stability Analysis Using a Full Wave Code US-Japan JIFT Workshop on Progress of Extended MHD Models NIFS, Toki,Japan 2007/03/27 MHD Linear Stability Analysis Using a Full Wave Code T. Akutsu and A. Fukuyama Department of Nuclear Engineering, Kyoto

More information

The Linear Theory of Tearing Modes in periodic, cyindrical plasmas. Cary Forest University of Wisconsin

The Linear Theory of Tearing Modes in periodic, cyindrical plasmas. Cary Forest University of Wisconsin The Linear Theory of Tearing Modes in periodic, cyindrical plasmas Cary Forest University of Wisconsin 1 Resistive MHD E + v B = ηj (no energy principle) Role of resistivity No frozen flux, B can tear

More information

TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings

TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings TH/P8-4 Second Ballooning Stability Effect on H-mode Pedestal Scalings T. Onjun 1), A.H. Kritz ), G. Bateman ), A. Pankin ) 1) Sirindhorn International Institute of Technology, Klong Luang, Pathumthani,

More information

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE T.H. Osborne 1, P.B. Snyder 1, R.J. Groebner 1, A.W. Leonard 1, M.E. Fenstermacher 2, and the DIII-D Group 47 th Annual Meeting

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

GTC Simulation of Turbulence and Transport in Tokamak Plasmas

GTC Simulation of Turbulence and Transport in Tokamak Plasmas GTC Simulation of Turbulence and Transport in Tokamak Plasmas Z. Lin University it of California, i Irvine, CA 92697, USA and GPS-TTBP Team Supported by SciDAC GPS-TTBP, GSEP & CPES Motivation First-principles

More information

Microtearing Simulations in the Madison Symmetric Torus

Microtearing Simulations in the Madison Symmetric Torus Microtearing Simulations in the Madison Symmetric Torus D. Carmody, P.W. Terry, M.J. Pueschel - University of Wisconsin - Madison dcarmody@wisc.edu APS DPP 22 Overview PPCD discharges in MST have lower

More information

Equilibrium and transport in Tokamaks

Equilibrium and transport in Tokamaks Equilibrium and transport in Tokamaks Jacques Blum Laboratoire J.-A. Dieudonné, Université de Nice Sophia-Antipolis Parc Valrose 06108 Nice Cedex 02, France jblum@unice.fr 08 septembre 2008 Jacques Blum

More information

L Aquila, Maggio 2002

L Aquila, Maggio 2002 Nonlinear saturation of Shear Alfvén Modes and energetic ion transports in Tokamak equilibria with hollow-q profiles G. Vlad, S. Briguglio, F. Zonca, G. Fogaccia Associazione Euratom-ENEA sulla Fusione,

More information

Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD

Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD 1 Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD Y. Todo 1), N. Nakajima 1), M. Osakabe 1), S. Yamamoto 2), D. A. Spong 3) 1) National Institute for Fusion Science,

More information

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Impact of neutral atoms on plasma turbulence in the tokamak edge region Impact of neutral atoms on plasma turbulence in the tokamak edge region C. Wersal P. Ricci, F.D. Halpern, R. Jorge, J. Morales, P. Paruta, F. Riva Theory of Fusion Plasmas Joint Varenna-Lausanne International

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

Integrated Transport Simulation Aiming at Burning Plasmas

Integrated Transport Simulation Aiming at Burning Plasmas Workshop on Transport and Confinement NIFS University, 2006/11/09 Integrated Transport Simulation Aiming at Burning Plasmas A. Fukuyama and M. Honda Department of Nuclear Engineering, Kyoto University

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

Lecture # 3. Introduction to Kink Modes the Kruskal- Shafranov Limit.

Lecture # 3. Introduction to Kink Modes the Kruskal- Shafranov Limit. Lecture # 3. Introduction to Kink Modes the Kruskal- Shafranov Limit. Steve Cowley UCLA. This lecture is meant to introduce the simplest ideas about kink modes. It would take many lectures to develop the

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

Turbulence in Tokamak Plasmas

Turbulence in Tokamak Plasmas ASDEX Upgrade Turbulence in Tokamak Plasmas basic properties and typical results B. Scott Max Planck Institut für Plasmaphysik Euratom Association D-85748 Garching, Germany Uni Innsbruck, Nov 2011 Basics

More information

Predictive Study on High Performance Modes of Operation in HL-2A 1

Predictive Study on High Performance Modes of Operation in HL-2A 1 1 EX/P-0 Predictive Study on High Performance Modes of Oration in HL-A 1 Qingdi GAO 1), R. V. BUDNY ), Fangzhu LI 1), Jinhua ZHANG 1), Hongng QU 1) 1) Southwestern Institute of Physics, Chengdu, Sichuan,

More information

Self-consistent modeling of ITER with BALDUR integrated predictive modeling code

Self-consistent modeling of ITER with BALDUR integrated predictive modeling code Self-consistent modeling of ITER with BALDUR integrated predictive modeling code Thawatchai Onjun Sirindhorn International Institute of Technology, Thammasat University, Klong Luang, Pathumthani, 12121,

More information

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg. Progressing Performance Tokamak Core Physics Marco Wischmeier Max-Planck-Institut für Plasmaphysik 85748 Garching marco.wischmeier at ipp.mpg.de Joint ICTP-IAEA College on Advanced Plasma Physics, Triest,

More information

Current-driven instabilities

Current-driven instabilities Current-driven instabilities Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 21 st February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously In the last

More information

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier EX/C-Rb Relationship between particle and heat transport in JT-U plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),

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

Critical gradient formula for toroidal electron temperature gradient modes

Critical gradient formula for toroidal electron temperature gradient modes PHYSICS OF PLASMAS VOLUME 8, NUMBER 9 SEPTEMBER 2001 Critical gradient formula for toroidal electron temperature gradient modes F. Jenko, W. Dorland, a) and G. W. Hammett b) Max-Planck-Institut für Plasmaphysik,

More information

Non-perturbative statistical theory of intermittency in ITG drift wave turbulence with zonal flows

Non-perturbative statistical theory of intermittency in ITG drift wave turbulence with zonal flows Non-perturbative statistical theory of intermittency in ITG drift wave turbulence with zonal flows Johan Anderson 1 and Eun-jin Kim University of Sheffield Department of Applied Mathematics Hicks Building,

More information

Active and Passive MHD Spectroscopy on Alcator C-Mod

Active and Passive MHD Spectroscopy on Alcator C-Mod Active and Passive MHD Spectroscopy on Alcator C-Mod J A Snipes, D A Schmittdiel, C Boswell, A Fasoli *, W Burke, R S Granetz, R R Parker, S Sharapov #, R Vieira MIT Plasma Science and Fusion Center, Cambridge,

More information

Progress in Modeling of ARIES ACT Plasma

Progress in Modeling of ARIES ACT Plasma Progress in Modeling of ARIES ACT Plasma And the ARIES Team A.D. Turnbull, R. Buttery, M. Choi, L.L Lao, S. Smith, General Atomics H. St John, G. Staebler C. Kessel Princeton Plasma Physics Laboratory

More information

DIII D I. INTRODUCTION QTYUIOP

DIII D I. INTRODUCTION QTYUIOP I. INTRODUCTION Among the endless surprises that the tokamak plasma has provided us, the formation of the transport barrier in the plasma interior is the least expected and the most interesting one Inside

More information

Heating and current drive: Radio Frequency

Heating and current drive: Radio Frequency Heating and current drive: Radio Frequency Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 13 th February 2012 Dr Ben Dudson Magnetic Confinement Fusion (1 of 26)

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

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

Predictions of fusion α-particle transport due to Alfvén eigenmodes in ITER

Predictions of fusion α-particle transport due to Alfvén eigenmodes in ITER Predictions of fusion α-particle transport due to Alfvén eigenmodes in ITER M. Fitzgerald, S.E. Sharapov, P. Rodrigues 2, A. Polevoi 3, D. Borba 2 2 Instituto de Plasmas e Fusão Nuclear, Instituto Superior

More information

UCIrvine. Gyrokinetic Studies of Turbulence Spreading IAEA-CN-116/TH1-4

UCIrvine. Gyrokinetic Studies of Turbulence Spreading IAEA-CN-116/TH1-4 AEA-CN-116/TH1-4 Gyrokinetic Studies of Turbulence Spreading T.S. Hahm, Z. Lin, a P.H. Diamond, b G. Rewoldt, W.X. Wang, S. Ethier, O. Gurcan, b W. Lee, and W.M. Tang Princeton University, Plasma Physics

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

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

Simple examples of MHD equilibria

Simple examples of MHD equilibria Department of Physics Seminar. grade: Nuclear engineering Simple examples of MHD equilibria Author: Ingrid Vavtar Mentor: prof. ddr. Tomaž Gyergyek Ljubljana, 017 Summary: In this seminar paper I will

More information

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT PROGRAM C-Mod C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER C-MOD - OPPORTUNITIES AND CHALLENGES Prediction and control are the ultimate goals

More information

Comparison of theory-based and semi-empirical transport modelling in JET plasmas with ITBs

Comparison of theory-based and semi-empirical transport modelling in JET plasmas with ITBs INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion (). p. PLASMA PHYSICS AND CONTROLLED FUSION PII: S7-()9-X Comparison of theory-based and semi-empirical transport modelling in JET plasmas with

More information

Curvature transition and spatiotemporal propagation of internal transport barrier in toroidal plasmas

Curvature transition and spatiotemporal propagation of internal transport barrier in toroidal plasmas Curvature transition and spatiotemporal propagation of internal transport barrier in toroidal plasmas K.Ida, JT- Team a and LHD experiment Group National Institute for Fusion Science, Toki 59-59 Japan

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

Nonlinear Zonal Dynamics of Drift and Drift-Alfvén Turbulences in Tokamak Plasmas

Nonlinear Zonal Dynamics of Drift and Drift-Alfvén Turbulences in Tokamak Plasmas Nonlinear Zonal Dynamics of Drift and Drift-Alfvén Turbulences in Toama Plasmas Liu Chen, Zhihong Lin, Roscoe B. White and Fulvio Zonca Department of Physics and Astronomy, University of California, Irvine,

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

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling G. Vlad, S. Briguglio, G. Fogaccia, F. Zonca Associazione Euratom-ENEA

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

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu

More information

Non-ohmic ignition scenarios in Ignitor

Non-ohmic ignition scenarios in Ignitor Non-ohmic ignition scenarios in Ignitor Augusta Airoldi IFP, EURATOM-ENEA-CNR Association, Milano, Italy Francesca Bombarda, Giovanna Cenacchi Ignitor Group, ENEA, Italy Bruno Coppi MIT, USA DPP1 APS Meeting

More information

Comparative Transport Analysis of JET and JT-60U Discharges

Comparative Transport Analysis of JET and JT-60U Discharges EFDA JET CP(1)/13 J. Garcia, N. Hayashi, G. Giruzzi, M. Schneider, E. Joffrin, S. Ide, Y. Sakamoto, T. Suzuki, H. Urano, the JT-U Team and JET EFDA contributors Comparative Transport Analysis of JET and

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

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

PROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIIIÐD *

PROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIIIÐD * PROGRESS TOWARDS SUSTAINMENT OF ADVANCED TOKAMAK MODES IN DIIIÐD * B.W. RICE, K.H. BURRELL, J.R. FERRON, C.M. GREENFIELD, G.L. JACKSON, L.L. LAO, R.J. LA HAYE, T.C. LUCE, B.W. STALLARD, E.J. STRAIT, E.J.

More information

Waves in plasma. Denis Gialis

Waves in plasma. Denis Gialis Waves in plasma Denis Gialis This is a short introduction on waves in a non-relativistic plasma. We will consider a plasma of electrons and protons which is fully ionized, nonrelativistic and homogeneous.

More information

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model 1 THC/3-3 ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model J.E. Kinsey, G.M. Staebler, J. Candy, and R.E. Waltz General Atomics, P.O. Box 8608, San Diego, California

More information

Fine-Scale Zonal Flow Suppression of Electron Temperature Gradient Turbulence

Fine-Scale Zonal Flow Suppression of Electron Temperature Gradient Turbulence Fine-Scale Zonal Flow Suppression of Electron Temperature Gradient Turbulence S.E. Parker, J.J. Kohut, Y. Chen, Z. Lin, F.L. Hinton and W.W. Lee Center for Integrated Plasma Studies, University of Colorado,

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

Studies of Turbulence-driven FLOWs:

Studies of Turbulence-driven FLOWs: Studies of Turbulence-driven FLOWs: a) V ", V Competition in a Tube b) Revisiting Zonal Flow Saturation J.C. Li, P.H. Diamond, R. Hong, G. Tynan University of California San Diego, USA This material is

More information

Nonlinear Simulation of Energetic Particle Modes in JT-60U

Nonlinear Simulation of Energetic Particle Modes in JT-60U TH/P6-7 Nonlinear Simulation of Energetic Particle Modes in JT-6U A.Bierwage,N.Aiba 2, K.Shinohara 2, Y.Todo 3,W.Deng 4,M.Ishikawa 2,G.Matsunaga 2 and M. Yagi Japan Atomic Energy Agency (JAEA), Rokkasho,

More information