Integrated Tokamak Code: TASK
|
|
- Nora Cooper
- 5 years ago
- Views:
Transcription
1 2010/01/18 Integrated Tokamak Code: TASK A. Fukuyama Department of Nuclear Engineering, Kyoto University Acknowledgments M. Honda, H. Nuga, and BPSI working group
2 Outline 1. Integrated Simulation of Fusion Plasmas 2. Integrated Tokamak Modeling Code: TASK 3. Transport Modeling 4. Source Modeling 5. ITER Modeling 6. Summary
3 Integrated Simulation of Toroidal Plasmas Why needed? To predict the behavior of burning plasmas in tokamaks To develop reliable and efficient schemes to control them What is needed? Simulation describing: Whole plasma (core & edge & divertor & wall-plasma) Whole discharge (startup & sustainment & transients events & termination) Reasonable accuracy (validation by experiments) Reasonable computer resources (still limited) How can we do? Gradual increase of understanding and accuracy Organized development of simulation system
4 Simulation of Tokamak Plasmas Broad range of time scale: 100GHz 1000s Broad range of Spatial scale: 10 μm 10m Energetic Ion Confinement Transport Barrier Core Transport MHD Stability Non-Inductive CD LENGTH 1m 1mm Heating LH EC IC MHD Transport NBI Turbulence Turbulent Transport Impurity Transport SOL Transport RF Heating NBI Heating Neutral Transport 1GHz 1MHz TIME 1kHz 1Hz Divertor Plasma Plasma-Wall Int. One simulation code never covers all range. Blanket, Neutronics, Tritium, Material, Heat and Fluid Flow Integrated simulation combining modeling codes interacting each other
5 Integrated Tokamak Simulation
6 Desired Features of Integrated Modeling Code Modular structure: forflexible extension of analyses Core modules (equilibrium, transport, source, stability) Various levels of models (quick, standard, precise, rigorous) New physics models (easier development) Standard module interface: for efficient development-of modules Interface with experimental data: for validating physics models Unified user interface: for user-friendly environment Scalability in parallel processing of time consuming modules High portability Open source of core modules Visualization included
7 Integrated Modeling Activities Japan: BPSI (Burning Plasma Simulation Initiative) Research collaboration among universities, NIFS and JAEA Framework for code integration Physics integration Advanced computing technology EU: ITM-TF (EFDA Task Force: Integrated Transport Modeling) Code Platform Project: code interface, data structure Data Coordination Project: verification and validation Five Integrated Modeling Projects: EQ, MHD, TR, Turb., Source US: FSP (Fusion simulation project) a part of SciDAC Simulation of Wave Interactions with Magnetohydrodynamics (SWIM) Center for Plasma Edge Simulation (CPES) Framework Application for Core-Edge Transport Simulations (FACETS) ITER: IMEG (Integrated Modeling Expert Group)
8 BPSI: Burning Plasma Simulation Initiative Research Collaboration of Universities, NIFS and JAEA Targets of BPSI Framework for collaboration of various plasma simulation codes Physics integration with different time and space scales Advanced technique of computer science All Japan collaboration Integrated code development
9 Integrated Modeling Code: TASK Transport Analysing System for TokamaK Features Core of Integrated Modeling Code in BPSI Modular structure Reference imprementation of standard data set and interface Various Heating and Current Drive Scheme EC, LH, IC, AW, NB High Portability Most of library routines included (except LAPACK, MPI, MDS+) Original graphic libraries (X11, Postscript, OpenGL) Development using CVS (Version control) Open Source: Parallel Processing using MPI Library (partially)
10 Components of the TASK Code Developed since 1992, now in Kyoto University BPSD Data Exchange Standard data set, Program interface EQ 2D Equilibrium Fixed boundary, Toroidal rotation TR 1D Transport Diffusive transport, Transport models TX 1D Transport Dynamic Transport, Rotation and E r FP 3D Fokker-Planck Relativistic, Bounce-averaged WR 3D Ray Tracing EC, LH: Ray tracing, Beam tracing WM 3D Full Wave IC: Antenna excite, Alfvén Eigenmode DP Wave Dispersion Dielectric tensor, Arbitrary f (u) FIT3D NBI Physics Birth, Orbit width, Deposition PL Utilities Interface to BPSD and profile database LIB Libraries Commonlibraries,MTX,MPI GSAF Graphics Original graphic library for Fortran TASK3D: Extension to 3D Helical Plasmas (NIFS and Kyoto U)
11 Original Structure of the TASK code
12 Present Structure of TASK and Related Codes in BPSI
13 Inter-Module Collaboration Interface Role of Module Interface Data exchange between modules: BPSD Standard dataset: Specify set of data Specification of data exchange interface: set/get/load/save Execution control: BPSX Specification of execution control interface: initialize, setup, exec, visualize, terminate Uniform user interface: parameter input, graphic output Role of data exchange interface Keep present status of plasma and device Save into file and load from file Store history of plasma Interface to experimental data base
14 Policies of BPSD Minimum and Sufficient Dataset To minimize the data to be exchanged Mainly profile data Routines to calculate global integrated quantities separately provided Minimum Arguments in Interfaces To maximize flexibility Use derived data type or struct Only one dataset in the arguments of an interface Minimum Interfaces To make modular programming easier Use function overloading
15 Data Exchange Interface: BPSD Standard dataset: Specify data to be stored and exchanged Data structure: Derived type (Fortran95): structured type e.g. Specification of API: Program interface e.g. time plasmaf%time number of grid plasmaf%nrmax number of species plasmaf%nsmax square of grid radius plasmaf%s(nr) plasma density plasmaf%data(nr,ns)%pn plasma temperature plasmaf%data(nr,ns)%pt Set data bpsd set data(plasmaf,ierr) Get data bpsd get data(plasmaf,ierr) Save data bpsd save(ierr) Load data bpsd load(ierr)
16 BPSD Standard Dataset (version 0.6) Category Name EQ TR TX FP WR WM DP Shot data bpsd shot type Device data bpsd device type in in in in 1D equilibrium data bpsd equ1d type out in in in 2D equilibrium data bpsd equ2d type out in in in in 1D metric data bpsd metric1d type out in in in 2D metric data bpsd metric2d type out in in in in Plasma species data bpsd species type in in in in in Fluid plasma data bpsd plasmaf type in out out i/o in Kinetic plasma data bpsd plasmak type out in Transport matrix data bpsd trmatrix type i/o Transport source data bpsd trsource type i/o i/o i/o out out Dielectric tensor data bpsd dielectric type in in out Full wave field data bpsd wavef type in out Ray tracing field data bpsd waver type in out Beam tracing field data bpsd waveb type in out User defined data bpsd 0/1/2ddata type
17 Execution Control Interface BPSX: not yet decided Monolithic integrated code Script-driven element codes MPI-2 driven element codes Example of element codes for TASK/TR TR INIT Initialization (Default value) TR PARM(ID,PSTR) Parameter setup (Namelist input) TR SETUP(T) Profile setup (Spatial profile, Time) TR EXEC(DT) Exec one step (Time step) TR GOUT(PSTR) Plot data (Plot command) TR SAVE Save data in file TR LOAD load data from file TR TERM Termination
18 Equilibrium Analysis Shape of an axisymmetric plasma: poloidal magnetic flux ψ(r, Z) Grad-Shafranov equation R 1 ψ RR R + 2 ψ Z 2 = μ 0R 2dp(ψ) dψ Pressure profile: p(ψ) Poloidal current density profile: F(ψ) Plasma boundary shape (fixed boundary) or Poloidal coil current (free boundary) F(ψ)dF(ψ) dψ determines the poloidal plasma shape. Coupling with transport analysis Input: p(ψ), q(ψ) = F dv 1 dψ R 2 Output: Metric quantities, Flux surface averaged quantities
19 Various Levels of Transport Modeling
20 Transport Modeling in the TASK code Diffusive transport equation: TASK/TR Diffusion equation for plasma density Flux-Gradient relation Conventional transport analysis Dynamical transport equation: TASK/TX: Continuity equation and equation of motion for plasma density Flux-averaged fluid equation Plasma rotation and transient phenomena Kinetic transport equation: TASK/FP: Gyrokinetic equation for momentum distribution function Bounce-averaged Fokker-Plank equation Modification of momentum distribution
21 Diffusive Transport Equation: TASK/TR Transport Equation Based on Gradient-Flux Relation: Γ = M F/ ρ where V: Volume, ρ: Normalized radius, V = dv/dρ Particle transport 1 V t (n sv ) = ( ) V ρ n s V s V ρ 2 n s D s ρ ρ + S s Toroidal momentum transport 1 V t (n su φs V ) = ( ) V ρ n s u φs V Ms V ρ 2 u φs n z μ s ρ ρ Heat transport ( ) 1 3 V 5/3 t 2 n st s V 5/3 Current diffusion B θ = [ t ρ η FR 0 R 2 + M s = 1 ( V ρ 3 ) V ρ 2 n st s V Es V ρ 2 T s n s χ s ρ R 0 F 2 ( V B θ μ 0 V ρ F ) ρ 2 R 2 ] η FR 0 R 2 J B ext + P s
22 Transport Processes Neoclassical transport Collisional transport in an inhomogeneous magnetic field Radial diffusion: usually small compared with turbulent diffusion Enhanced resistivity: due to trapped particles Bootstrap current: toroidal current driven by radial pressure gradient Ware pinch: Radial particle pinch driven by toroidal electric field Turbulent transport Various transport models: GLF23, CDBM, Weiland, Atomic transport: charge exchange, ionization, recombination Radiation transport Line radiation, Bremsstrahlung, Synchrotron radiation Parallel transport: along open magnetic field lines in SOL plasmas
23 Turbulent Transport Models CDBM model: current diffusive ballooning mode turbulence model developed by K. Itoh et al. Marginal stability condition of the current diffusive ballooning mode including turbulent transport coefficients as parameters GLF23 model: Gyro-Landau-Fluid turbulence model developed by Waltz and Kinsey (GA) Linear growth rate from gyro-landau-fluid model (ITG, TEM, ETG) Evaluate transport coefficients based on mixing length estimate Calibrate coefficients by the linear stability code GKS Calibrate coefficients by the nonlinear turbulence code GYRO Weiland model: developed by J. Weiland Based on ITG turbulence model
24 GLF23 Transport Model Linear growth rate from gyro-landau-fluid model Calibrate coefficients by the nonlinear turbulence code GYRO Good agreement with experimental data
25 CDBM Transport Model: CDBM05 Thermal Diffusivity (Marginal: γ = 0) χ TB = F(s,α,κ,ω E1 ) α 3/2 c2 ω 2 pe v A qr s α dependence of F(s,α,κ,ω E1 ) ω E1 =0 ω E1 =0.1 Magnetic shear s r dq q dr Pressure gradient α q 2 R dβ dr Elongation κ b/a E B rotation shear ω E1 r2 d E sv A dr rb Weak and negative magnetic shear, Shafranov shift, elongation, and E B rotation shear reduce thermal diffusivity. F ω E1 =0.2 ω E1 = F(s,α,κ,ω E1 ) = s - α ( 2κ 1/2 1 + κ 2 ) 3/ G 1 ω 2 E1 2(1 2s )(1 2s + 3s 2 ) for s = s α< s 5/2 1 + G 1 ω 2 E1 2(1 2s + 3s 2 + 2s 3 ) for s = s α>0
26 TFTR #88615 (L-mode, NBI heating)
27 DIII-D #78316 (L-mode, ECH and ICH heatings)
28 Comparison of Transport Models: ITPA Profile DB Deviation of Stored Energy CDBM CDBM05 GLF23 Weiland
29 1D Dynamic Transport Code: TASK/TX Dynamic Transport Equations (TASK/TX) M. Honda and A. Fukuyama, JCP 227 (2008) 2808 A set of flux-surface averaged equations Two fluid equations for electrons and ions Continuity equations Equations of motion (radial, poloidal and toroidal) Energy transport equations Maxwell s equations Slowing-down equations for beam ion component Diffusion equations for two-group neutrals Self-consistent description of plasma rotation and electric field Equation of motion rather than transport matrix Quasi-neutrality is not assumed.
30 Model Equation of Dynamic Transport Simulation Flux-surface-averaged multi-fluid equations: n s t = 1 r r (rn su sr ) + S s t (m sn s u sr )= 1 r r (rm sn s u 2 sr ) + 1 r m sn s u 2 sθ + e sn s (E r + u sθ B φ u sφ B θ ) r n st s t (m sn s u sθ )= 1 r 2 r (r2 m s n s u sr u sθ ) + e s n s (E θ u sr B φ ) + 1 ( r 3 n r 2 s m s μ s r r +F NC sθ ( ) 1 ms n s u sφ = t r + F C sθ + F W sθ + F X sθ + F L sθ r (rm sn s u sr u sφ ) + e s n s (E φ + u sr B θ ) + 1 r r ( ) rn s m s μ s r u sφ ) u sθ r t 3 2 n st s = 1 r +F C sφ + FW sφ + FX sφ + FL sφ ( ) 5 r r 2 u srn s T s n s χ s r T e + e s n s (E θ u sθ + E φ u sφ ) +P C s + P L s + P H s
31 Typical Ohmic Plasma Profiles at t = 50 ms JFT-2M like plasma composed of electron and hydrogen R = 1.3m, a = 0.35 m, b = 0.4m, B φb = 1.3T, I p = 0.2MA, S puff = m 2 s 1 γ = 0.8, Z eff = 2.0, Fixed turbulent coefficient profile E r (r) [kv/m] E 0.2 θ [mv/m] E φ [kv/m] B θ [T] B φ [T] n e [10 20 m -3 ] T e [kev] T i [kev] n 01 [10 14 m -3 ] n 02 [10 10 m -3 ] u er [m/s] u eθ [km/s] u eφ [km/s] D e [m 2 /s] χ e =χ i =μ e =μ i [m 2 /s] u ir [m/s] u iθ [km/s] u iφ [km/s] q j φ [MA/m 2 ] 0.0
32 Density Profile Modification Due to NBI Injection Modification of n and E r profile depends on the direction of NBI E r [kv/m] u bφ [km/s] q Co/Counter with I p : Density flattening/peaking n e [10 20 m -3 ] u er [km/s] j φ [MA/m 2 ] no NBI co counter T e [kev] u eθ [km/s] u iθ [km/s] T i [kev] 0.0 u eφ [km/s] u iφ [km/s]
33 Toroidal Rotation Due to Ion Orbit Loss Ion orbit loss near the edge region drives toroidal rotation Ref. M. Honda et al., NF (2008)
34 Source Modeling Heat and momentum sources: Alpha particle heating: sensitive to fuel density and momentum distribution Neutral beam injection: birth profile, finite size orbit, deposition to bulk plasma Waves: IC ( 50 MHz): fuel ion heating, current drive, rotation drive(?) LH ( 10 GHz): current drive EC ( 170 GHz): current drive, pre-ionization Particle source Gas puff, recycling: Neutral beam injection: Pellet injection: penetration, evaporation, ionization, drift motion
35 Wave Modeling Ray tracing: EC, LH Spatial evolution of ray position and wave number Wave length λ much less than scale length L: λ L Beam size d is sufficiently large (Fresnel condition): L d 2 /λ Beam tracing: EC New variables: beam radius, curvature of equi-phase surface Beam propagation: EC Under development: Time evolution of E(r, t)e i ωt Full wave analysis: IC, AW, MHD Stationary Maxwell s equation as a boundary problem Wave length λ comparable with scale length L Evanescent region, strong absorption, coupling with antenna
36 Wave Dispersion Analysis : TASK/DP Various Models of Dielectric Tensor ɛ (ω, k; r): Analytic model Resistive MHD model Collisional cold plasma model Collisional warm plasma model Kinetic model (Maxwelian, non-relativistic) Drift-kinetic model (Maxwellian, inhomogeneity) Hamiltonian formulation (cyclotron, bounce, precession) Numerical integrateion Kinetic model (Relativistic, Maxwellian) Kinetic model (Relativistic, arbitrary f (u)) Drift-kinetic model (Inhoogeneity, arbitrary f (u)) Hamiltonian formulation (arbitrary f (u)))
37 Geometrical Optics Ray Tracing: TASK/WR Wave length λ Characteristic scale length L of the medium Plane wave: Beam size d is sufficiently large Fresnel condition is well satisfied: L d 2 /λ Evolution along the ray trajectory τ Wave packet position r, wave number k, dielectric tensor K Ray tracing equation: dr dτ = K / K k ω dk dτ = K / K r ω Equation for wave energy W, group velocity u g, damping rate γ (u g W ) = 2γW
38 Beam Tracing: TASK/WR Beam size perpendicular to the beam direction: first order in ɛ Beam shape : Hermite polynomial: H n ) [ ] E(r) = Re C mn (ɛ 2 r)e(ɛ 2 r)h m (ɛξ 1 )H n (ɛξ 2 )e i s(r) φ(r) mn Amplitude : C mn, Polarization : e, Phase : s(r) + i φ(r) s(r) = s 0 (τ) + k 0 α(τ)[r α r α 0(τ)] s αβ[r α r α 0(τ)][r β r β 0 (τ)] φ(τ) = 1 2 φ αβ[r α r α 0(τ)][r β r β 0 (τ)] Position of beam axis : r 0, Wave number on beam axis: k 0 Curvature radius of equi-phase surface: R α = 1/λs αα Beam radius: d α = 2/φ αα R 1 d 1 Gaussian beam : case with m = 0, n = 0 R 2 d 2
39 Beam Propagation Equation Solvable condition for Maxwell s equation with beam field dr α 0 dτ = K k α dk 0 α dτ = K r α ds αβ dτ = 2 K r α r β dφ αβ dτ = ( 2 K r α k γ + 2 K r β k γ s αγ 2 K k γ k δ s αδ 2 K s r α βγ k γ ) φ βγ ( 2 K r β k γ + 2 K k γ k δ s αγs βδ + 2 K k γ k δ s βδ 2 K k γ k δφ αγφ βδ ) By integrating this set of 18 ordinary differential equations, we obtain trace of the beam axis, wave number on the beam axis, curvature of equi-phase surface, and beam size. Equation for the wave amplitude C mn (u g0 C mn 2) = 2 ( γ C mn 2) Group velocity: u g0, Damping rate: γ (e ɛ A e)/( K/ ω) φ αγ
40 Full wave analysis: TASK/WM magnetic surface coordinate: (ψ, θ, ϕ) Boundary-value problem of Maxwell s equation Kinetic dielectric tensor: ɛ E = ω2 c 2 ɛ E + i ωμ0 j ext Wave-particle resonance: Z[(ω nω c )/k v th ] Fast ion: Drift-kinetic [ t + v + (u d + u E ) + e α (v m E + u d E) ] α ε f α = 0 Poloidal and toroidal mode expansion Accurate estimation of k Eigenmode analysis: Complex eigen frequency whichmaximize wave amplitude for fixed excitation proportional to electron density
41 Fokker-Planck Analysis : TASK/FP Fokker-Planck equation for multi-species velocity distribution function: f s (p, p,ψ,t) f s = E( f s ) + C( f s ) + Q( f s ) + L( f s ) t E( f ): Acceleration term due to DC electric field C( f ): Coulomb collision term Q( f ): Quasi-linear term due to wave-particle resonance L( f ): Spatial diffusion term Bounce-averaged: Trapped particle effect, zero banana width Relativistic: momentum p, weakly relativistic collision term Nonlinear collision: momentum and energy conservation Multi-species: conservation between species Three-dimensional: spatial diffusion (neoclassical, turbulent)
42 ITER Modeling Needs based on Dr. Campbell talk at Cadarache, Sept 2007 Plasma scenario development: Preparation for operation Detailed design of auxiliary systems: H&CD, Diagnostics, Fueling, Design of plasma control system: Development and optimization of integrated control strategies Preparation of ITER operational programme: End-to-end scenario development Detailed pulse definition Experimental data evaluation: Pulse characterization and physics analysis Refinement of operation scenario and performance predictions
43 Analysis of EC propagation in ITER BB = RR = RA = RKAP = Q0 = QA = RF = 1.700E+05 NPHII= PA(1) = PZ(1) = PN(1) = PNS(1) = PTPR(1)= PTPP(1)= PTS(1) = MODELP1= 25. PA(2) = PZ(2) = PN(2) = PNS(2)= PTPR(2)= PTPP(2)= PTS(2) = MODELP2= 1. 4 ABS POWER ABS WEIGHT POWER
44 Analysis of IC propagation in ITER Minority heating in D phase: D+H Radial profile Wave electric field P abs by minority ion
45 ITER Plasma Transport Simulation with CDBM05 Inductive operation I p = 15 MA P NB = 40 MW on axis β N = 2.65 Hybrid operation I p = 12 MA P NB = 33 MW on axis β N = 2.68 Time evolution Radial profile Time evolution Radial profile
46 Alfvén Eigenmode Analysis by TASK/WM Alfvén eigenmode driven by alpha particles Calculated by the full wave module TASK/WM Toroidal mode number: n = 1 TAE is stable: Eigen mode frequency = (95.95 khz, 1.95 khz) Alfvén continuum frequency Alfvén eigenmode structure Alpha particle density
47 ITER Inductive Operation 15 MA Current rise in 70 s Behavior of plasma depends on timing of heating
48 Future Plan of the TASK code
49 Remaining Issues in Tokamak Plasma Modling Pedestal temperature: Transport barrier formation: ELM physics: Nonlinear MHD events: modeling of L/H transition turbulence transport model nonlinear behavior of ELM on transport modeling of plasma profile change Energetic-ion driven phenomena: coupling of Alfvén mode and drift waves Kinetic analysis of transport and MHD phenomena: non-maxwellian distribution Wave physics: full wave analysis of Bernstein waves Divertor plasma: Start up: and so on... plasma-wall interaction Rapid change of equilibrium and control
50 Summary Integrated modeling of burning plasmas is indispensable for exploiting optimized operation scenario of ITER and reliable design of DEMO. Discussion on international collaboration for the development of integrated ITER modeling is on going. There are many remaining issues in constructing comprehensive integrated code; especially, L/H transition mechanism, turbulent transport model, ELM physics, nonlinear MHD events, energetic particle driven phenomena and plasma wall-interactions. Solving those remaining issues requires not only large-scale computer simulations but also intensive modeling efforts based on experimental observations.
Integrated Modelling and Simulation of Toroidal Plasmas
7th ITER International School on High performance computing in fusion science Aix-Marseille University, Aix-en-Provence, France 2014-08-28 Integrated Modelling and Simulation of Toroidal Plasmas Atsushi
More informationIntegrated 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 informationIntegrated Full Wave Analysis of RF Heating and Current Drive in Toroidal Plasmas
Integrated Full Wave Analysis of RF Heating and Current Drive in Toroidal Plasmas IAEA Fusion Energy Conference Chengdu, China 2006/10/20 A. Fukuyama, S. Murakami, A. Sonoda, M. Honda// Department of Nuclear
More informationTASK: Integrated Simulation Code
Workshop on Kinetic Theory in Stellarators Kyoto University, 2006/09/20 TASK: Integrated Simulation Code A. Fukuyama and M. Honda Department of Nuclear Engineering, Kyoto University presented by N. Nakajima
More informationIntegrated Full-Wave Modeling of ICRF Heating in Tokamak Plasmas
EPS PPC 2007, Warsaw, Poland D1-005, 2007/07/02 Integrated Full-Wave Modeling of ICRF Heating in Tokamak Plasmas A. Fukuyama, S. Murakami, T. Yamamoto, H. Nuga Department of Nuclear Engineering, Kyoto
More informationPresent Status and Future Plan of TASK Code
Fifth BPSI meeting RIAM, Kyushu Univ, 2006/12/21 Present Status and Future Plan of TASK Code A. Fukuyama Department of Nuclear Engineering, Kyoto University in collaboration with M. Yagi and M. Honda Contents
More informationIntegrated 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 informationDirect drive by cyclotron heating can explain spontaneous rotation in tokamaks
Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual
More informationHeating 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 informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationRecent Progress in Integrate Code TASK
US-Japan JIFT Workshop on Integrated Modeling on Fusion Plasmas ORNL, Oak Ridge, USA 2007/01/29 Recent Progress in Integrate Code TASK Integrated Modeling of RF Heating and Current Drive in Tokamaks A.
More informationModeling of Transport Barrier Based on Drift Alfvén Ballooning Mode Transport Model
9th IAEA TM on H-mode Physics and Transport Barriers Catamaran Resort Hotel, San Diego 3-9-5 Modeling of Transport Barrier Based on Drift Alfvén Ballooning Mode Transport Model A. Fukuyama, M. Uchida and
More informationCurrent 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 informationMHD 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 informationIntegrated Particle Transport Simulation of NBI Plasmas in LHD )
Integrated Particle Transport Simulation of NBI Plasmas in LHD Akira SAKAI, Sadayoshi MURAKAMI, Hiroyuki YAMAGUCHI, Arimitsu WAKASA, Atsushi FUKUYAMA, Kenichi NAGAOKA 1, Hiroyuki TAKAHASHI 1, Hirohisa
More informationFormation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )
Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University
More informationRotation and Neoclassical Ripple Transport in ITER
Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics
More informationLocalized Electron Cyclotron Current Drive in DIII D: Experiment and Theory
Localized Electron Cyclotron Current Drive in : Experiment and Theory by Y.R. Lin-Liu for C.C. Petty, T.C. Luce, R.W. Harvey,* L.L. Lao, P.A. Politzer, J. Lohr, M.A. Makowski, H.E. St John, A.D. Turnbull,
More informationOverview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations
Overview of Tokamak Rotation and Momentum Transport Phenomenology and Motivations Lecture by: P.H. Diamond Notes by: C.J. Lee March 19, 2014 Abstract Toroidal rotation is a key part of the design of ITER
More informationEnergetic Particle Physics in Tokamak Burning Plasmas
Energetic Particle Physics in Tokamak Burning Plasmas presented by C. Z. (Frank) Cheng in collaboration with N. N. Gorelenkov, G. J. Kramer, R. Nazikian, E. Fredrickson, Princeton Plasma Physics Laboratory
More informationIntegration of Fokker Planck calculation in full wave FEM simulation of LH waves
Integration of Fokker Planck calculation in full wave FEM simulation of LH waves O. Meneghini S. Shiraiwa R. Parker 51 st DPP APS, Atlanta November 4, 29 L H E A F * Work supported by USDOE awards DE-FC2-99ER54512
More informationTURBULENT 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 informationAdvanced 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 informationNon-Solenoidal Plasma Startup in
Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique
More informationMHD-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 informationITER 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 informationComparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )
Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI
More informationModeling 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 informationExperimental evaluation of nonlinear collision effect on the beam slowing-down process
P-2 Experimental evaluation of nonlinear collision effect on the beam slowing-down process H. Nuga R. Seki,2 S. Kamio M. Osakabe,2 M. Yokoyama,2 M. Isobe,2 K. Ogawa,2 National Institute for Fusion Science,
More informationBounce-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 informationTheory Work in Support of C-Mod
Theory Work in Support of C-Mod 2/23/04 C-Mod PAC Presentation Peter J. Catto for the PSFC theory group MC & LH studies ITB investigations Neutrals & rotation BOUT improvements TORIC ICRF Mode Conversion
More informationA 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 informationStudies of Lower Hybrid Range of Frequencies Actuators in the ARC Device
Studies of Lower Hybrid Range of Frequencies Actuators in the ARC Device P. T. Bonoli, Y. Lin. S. Shiraiwa, G. M. Wallace, J. C. Wright, and S. J. Wukitch MIT PSFC, Cambridge, MA 02139 59th Annual Meeting
More informationTRANSPORT 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 informationSelf-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 informationMHD. Jeff Freidberg MIT
MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium
More informationOVERVIEW OF THE ALCATOR C-MOD PROGRAM. IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center
OVERVIEW OF THE ALCATOR C-MOD PROGRAM IAEA-FEC November, 2004 Alcator Team Presented by Martin Greenwald MIT Plasma Science & Fusion Center OUTLINE C-Mod is compact, high field, high density, high power
More informationPlasma shielding during ITER disruptions
Plasma shielding during ITER disruptions Sergey Pestchanyi and Richard Pitts 1 Integrated tokamak code TOKES is a workshop with various tools objects Radiation bremsstrahlung recombination s line s cyclotron
More informationRecent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science
Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant
More informationUnderstanding 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 informationSimulation 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 informationIntroduction to Plasma Physics
Introduction to Plasma Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 A simplistic view on a Fusion Power
More informationDer Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk
Max-Planck-Institut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator
More informationCharacteristics 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 informationImpact 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 informationEffects 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 informationSUMMARY 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 informationExperimental analysis and predictive simulation of heat transport using TASK3D code
Experimental analysis and predictive simulation of heat transport using TASK3D code A. Wakasa 1, A. Fukuyama 2, S. Murakami 2, N. Takeda 2, and, M. Yokoyama 3 1 Research Organization for Information Science
More informationGTC 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 informationBenchmarking of electron cyclotron heating and current drive codes on ITER scenarios within the European Integrated Tokamak Modelling framework
Benchmarking of electron cyclotron heating and current drive codes on ITER scenarios within the European Integrated Tokamak Modelling framework L. Figini 1,a, J. Decker 2, D. Farina 1, N. B. Marushchenko
More informationProgressing 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 informationLower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation
Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod
More informationIntroduction 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 informationActive 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 informationPredicting the Rotation Profile in ITER
Predicting the Rotation Profile in ITER by C. Chrystal1 in collaboration with B. A. Grierson2, S. R. Haskey2, A. C. Sontag3, M. W. Shafer3, F. M. Poli2, and J. S. degrassie1 1General Atomics 2Princeton
More informationStudy of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.
Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0. Igor Bespamyatnov, William Rowan, Ronald Bravenec, and Kenneth Gentle The University of Texas at Austin,
More informationJoint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics October Introduction to Fusion Leading to ITER
2267-1 Joint ITER-IAEA-ICTP Advanced Workshop on Fusion and Plasma Physics 3-14 October 2011 Introduction to Fusion Leading to ITER SNIPES Joseph Allan Directorate for Plasma Operation Plasma Operations
More informationStudies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D
Studies of H Mode Plasmas Produced Directly by Pellet Injection in by P. Gohil in collaboration with L.R. Baylor,* K.H. Burrell, T.C. Jernigan,* G.R. McKee, *Oak Ridge National Laboratory University of
More informationAnalysis 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 informationGenerating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN,
Generating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN, 14.10.2015 Paula Sirén VTT Technical Research Centre of Finland, P.O Box 1000, 02044
More informationFull-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak
Full-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak P. T. BONOLI, J. P. LEE, S. SHIRAIWA, J. C. WRIGHT, MIT-PSFC, B. DING, C. YANG, CAS-IPP, Hefei 57 th Annual Meeting of the APS
More informationA Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff
A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development
More informationOn Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas
1 On Electron-Cyclotron Waves in Relativistic Non-Thermal Tokamak Plasmas Lj. Nikolić and M.M. Škorić Vinča Institute of Nuclear Sciences, P.O.Box 522, Belgrade 11001, Serbia and Montenegro ljnikoli@tesla.rcub.bg.ac.yu
More informationImpact of Toroidal Flow on ITB H-Mode Plasma Performance in Fusion Tokamak
Impact of oroidal Flow on I H-Mode Plasma Performance in Fusion okamak oonyarit Chatthong 1,*, hawatchai Onjun 1, Roppon Picha and Nopporn Poolyarat 3 1 School of Manufacturing Systems and Mechanical Engineering,
More informationPredictive 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 informationInnovative 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 informationCharacteristics of Internal Transport Barrier in JT-60U Reversed Shear Plasmas
Characteristics of Internal Transport Barrier in JT-6U Reversed Shear Plasmas Y. Sakamoto, Y. Kamada, S. Ide, T. Fujita, H. Shirai, T. Takizuka, Y. Koide, T. Fukuda, T. Oikawa, T. Suzuki, K. Shinohara,
More informationC-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center
C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly
More information0 Magnetically Confined Plasma
0 Magnetically Confined Plasma 0.1 Particle Motion in Prescribed Fields The equation of motion for species s (= e, i) is written as d v ( s m s dt = q s E + vs B). The motion in a constant magnetic field
More informationEstimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD )
Estimations of Beam-Beam Fusion Reaction Rates in the Deuterium Plasma Experiment on LHD ) Masayuki HOMMA, Sadayoshi MURAKAMI, Hideo NUGA and Hiroyuki YAMAGUCHI Department of Nuclear Engineering, Kyoto
More informationToroidal confinement of non-neutral plasma. Martin Droba
Toroidal confinement of non-neutral plasma Martin Droba Contents Experiments with toroidal non-neutral plasma Magnetic surfaces CNT and IAP-high current ring Conclusion 2. Experiments with toroidal non-neutral
More informationImpact 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 informationExperimental Study of the Stability of Alfvén Eigenmodes on JET
IAEA FEC, Paper EX/P-7 Experimental Study of the Stability of Alfvén Eigenmodes on JET D.Testa,, A.Fasoli,, G.Fu 4, A.Jaun 3, D.Borba, P.de Vries 6, and JET-EFDA contributors [] Plasma Science and Fusion
More informationThe 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(a) (b) (c) (d) (e) (f) r (minor radius) time. time. Soft X-ray. T_e contours (ECE) r (minor radius) time time
Studies of Spherical Tori, Stellarators and Anisotropic Pressure with M3D 1 L.E. Sugiyama 1), W. Park 2), H.R. Strauss 3), S.R. Hudson 2), D. Stutman 4), X-Z. Tang 2) 1) Massachusetts Institute of Technology,
More informationEFFECT 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 informationWaves 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 informationDevelopment of LH wave fullwave simulation based on FEM
Development of LH wave fullwave simulation based on FEM S. Shiraiwa and O. Meneghini on behalf of LHCD group of Alacator C-Mod PSFC, MIT 2010/03/10 San-Diego, CA Special acknowledgements : R. Parker, P.
More informationTHE 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 informationC-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 informationRELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE
RELATIVISTIC EFFECTS IN ELECTRON CYCLOTRON RESONANCE HEATING AND CURRENT DRIVE Abhay K. Ram Plasma Science and Fusion Center Massachusetts Institute of Technology Cambridge, MA 02139. U.S.A. Joan Decker
More informationGyrokinetic 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 informationDispersive Media, Lecture 7 - Thomas Johnson 1. Waves in plasmas. T. Johnson
2017-02-14 Dispersive Media, Lecture 7 - Thomas Johnson 1 Waves in plasmas T. Johnson Introduction to plasmas as a coupled system Magneto-Hydro Dynamics, MHD Plasmas without magnetic fields Cold plasmas
More informationStudy of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD
21st IAEA Fusion Energy Conference Chengdu, China, 16-21 October, 2006 IAEA-CN-149/ Study of High-energy Ion Tail Formation with Second Harmonic ICRF Heating and NBI in LHD K. Saito et al. NIFS-851 Oct.
More informationZ. Lin University of California, Irvine, CA 92697, USA. Supported by SciDAC GPS-TTBP, GSEP & CPES
GTC Framework Development and Application Z. Lin University of California, Irvine, CA 92697, USA and dgpsttbp GPS-TTBP Team Supported by SciDAC GPS-TTBP, GSEP & CPES GPS-TTBP Workshop on GTC Framework
More informationShear Flow Generation in Stellarators - Configurational Variations
Shear Flow Generation in Stellarators - Configurational Variations D. A. Spong 1), A. S. Ware 2), S. P. Hirshman 1), J. H. Harris 1), L. A. Berry 1) 1) Oak Ridge National Laboratory, Oak Ridge, Tennessee
More information- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -
15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect
More informationStationary, 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 informationIntegrated modeling of LHCD non- induc6ve scenario development on Alcator C- Mod
Integrated modeling of LHCD non- induc6ve scenario development on Alcator C- Mod S. Shiraiwa, P. Bonoli, R. Parker, F. Poli 1, G. Wallace, and J, R. Wilson 1 PSFC, MIT and 1 PPPL 40th European Physical
More informationTriggering Mechanisms for Transport Barriers
Triggering Mechanisms for Transport Barriers O. Dumbrajs, J. Heikkinen 1, S. Karttunen 1, T. Kiviniemi, T. Kurki-Suonio, M. Mantsinen, K. Rantamäki 1, S. Saarelma, R. Salomaa, S. Sipilä, T. Tala 1 Euratom-TEKES
More informationGA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D
GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D by J.S. degrassie, D.R. BAKER, K.H. BURRELL, C.M. GREENFIELD, H. IKEZI, Y.R. LIN-LIU, C.C. PETTY, and R. PRATER APRIL 1997 This report
More informationDYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS
GA A23775 DYNAMICS OF THE FORMATION, SUSTAINMENT, AND DESTRUCTION OF TRANSPORT BARRIERS IN MAGNETICALLY CONTAINED FUSION PLASMAS by P. GOHIL NOVEMBER 2001 QTYUIOP DISCLAIMER This report was prepared as
More informationFull-wave Electromagnetic Field Simulations in the Lower Hybrid Range of Frequencies
Full-wave Electromagnetic Field Simulations in the Lower Hybrid Range of Frequencies P.T. Bonoli, J.C. Wright, M. Porkolab, PSFC, MIT M. Brambilla, IPP, Garching, Germany E. D Azevedo, ORNL, Oak Ridge,
More informationSpontaneous tokamak rotation: observations turbulent momentum transport has to explain
Spontaneous tokamak rotation: observations turbulent momentum transport has to explain Ian H Hutchinson Plasma Science and Fusion Center and Nuclear Science and Engineering Massachusetts Institute of Technology
More informationSawtooth mixing of alphas, knock on D, T ions and its influence on NPA spectra in ITER plasma
Sawtooth mixing of alphas, knock on D, T ions and its influence on NPA spectra in ITER plasma F.S. Zaitsev 1, 4, N.N. Gorelenkov 2, M.P. Petrov 3, V.I. Afanasyev 3, M.I. Mironov 3 1 Scientific Research
More informationITER 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 informationCharacterization 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 informationEFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY*
EFFECT OF PLASMA FLOWS ON TURBULENT TRANSPORT AND MHD STABILITY* by K.H. BURRELL Presented at the Transport Task Force Meeting Annapolis, Maryland April 3 6, 22 *Work supported by U.S. Department of Energy
More informationObservation of Neo-Classical Ion Pinch in the Electric Tokamak*
1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,
More informationTime-dependent Modeling of Sustained Advanced Tokamak Scenarios
Time-dependent Modeling of Sustained Advanced Tokamak Scenarios T. A. Casper, L. L. LoDestro and L. D. Pearlstein LLNL M. Murakami ORNL L.L. Lao and H.E. StJohn GA We are modeling time-dependent behavior
More information