Plasma Stability in Tokamaks and Stellarators

 Lenard Hodge
 5 months ago
 Views:
Transcription
1 Plasma Stability in Tokamaks and Stellarators Gerald A. Navratil GCEP Fusion Energy Workshop Princeton, NJ 1 May 006
2 ACKNOWLEDGEMENTS Borrowed VGs from many colleagues: J. Bialek, A. Garofalo,R. Goldston, A. Hubbard, R. Lahaye, J. Menard, H. Neilson, M. Okabayashi, E. J. Strait, S. Sabbagh, T. Taylor, M. Zarnstorff,
3 MHD EQUILIBRIUM AND STABILITY MHD Equilibrium requires: p = J x B MHD sets β limit Loss of equilibrium Sources of freeenergy for instability: Magnetic: B /µ o Pressure: nt Three primary limiting β phenomena: Long Wavelength Ideal Modes: n = 0, 1,, 3 Short Wavelength Ideal Modes: n Long Wavelength Resistive Modes: n = 1, Magnetic Reconnection: E + v x B = ηj
4 β LIMITING MODES: LOWn Must deal with long wavelength modes Shift & Tilt: n = 0 and 1 Kink: n = 1 n=0 mode: in tokamaks is solved with wall stabilization & active feedback control n=1 kink mode: limits determined to 10% to 0%. Tokamaks: solutions in hand using plasma rotation & active control. Stellarators: external magnetic field transform may allow sufficiently high beta below kink limit.
5 β LIMITING MODES: HIGHn Must deal with short wavelength ballooning/interchange modes, n Limits well understood and with 10% to 0% accuracy compared with experiments Controlled by plasma shape and magnetic shear profile:
6 β LIMITING MODES: TEARING MODES Must deal with long wavelength resistive tearing modes, n = 1,, Magnetic field line puncture plot showing island structure Tearing Modes: In tokamaks: stabilized by current profile control and active control with local ECH. In stellarators: controlled by tailoring external transform.
7 A COMPACT STEADY STATE TOKAMAK REQUIRES OPERATION AT HIGH β N P fus γ ε cur Q ss = eff β N B 3 aκ P CD nq ( 1 ξ A q β ) N β Power Density T ε 1 + κ DIII D NATIONAL FUSION FACILITY SAN DIEGO Current Limit q* = 4 Advanced Pressure Conventional Tokamak Limit Tokamak β N = 5 β N = 3.5 Equilibrium Limit εβ p Bootstrap Current High power density high β T Large bootstrap fraction high β p Steady state high β N β N power density bootstrap current ( 1 + κ β T β p )β N β N = β T /(I/aB) 130 0/TST/wj
8 PRIMARY LIMITING MODE IN MAGNETIC CONFINEMENT SYSTEMS: LOWn Kink Long wavelength global MHD modes driven by pressure & current gradient: Shift & Tilt: n = 0 and 1 Kink: n = 1 Classic Instability: Ideal conducting wall on plasma boundary stabilizes the kink mode by freezing magnetic flux value on wall surface. Resistive conducting wall stabilization fails on magnetic field soakthrough time scale: τ w
9 perturbed magnetic energy δw = 1 3 d x {ε c δb + ε c ( B ) (ξ δb) p Foundation of Kink Mode Stability Built on Energy Principle δw Stability Analysis 1957 Bernstein, Frieman, Kruskal, Kulsrud o } + ( ξ)(ξ p o ) + γp ( ξ) o pressure driven  destabilizing 1 δw = d x ε c δb current driven  destabilizing o plasma compression 3 o v vacuum perturbed magnetic energy If δw + δw < 0 mode is unstable p v
10 BASIC KINK MODE Long wavelength mode driven by pressure & current gradient Cylindrical k ~ π/l Toroidal: low n = 1 Unstable when δw p + δw v < 0 Dispersion Relation: γ K + δw p + δw v = 0, where K is kinetic fluid mass Define Γ = [δw p + δw v]/k ~ [v Alfvén /L]
11 IDEAL WALL STABILIZES THE KINK MODE Ideal wall traps field in vacuum region and restoring force stabilizes the kink EXTERNAL Kink: Unstable when δw p + δw d v < 0 Note: δw d v > δw v Dispersion Relation: γ  Γ + [δw d vδw v]/k = 0 Critical Wall Distance, d c, where kink stable for d < d c : simple [δw d vδw v]/k parameterization with d: γ  Γ [1 d c /d]/k = 0
12 KINK MODE IS STABILIZED BY IDEAL WALL 0 = γ Γ (1 d c) } Ideal Stability d γ / Γ ideal mode stable Ideal Instability γ Γ ideal mode unstable PlasmaWall Separation, d/d c /GAN/rs
13 RESISTIVE WALL LEAKS STABILIZING FIELD: τ W Stabilizing field decays resistively on wall time scale τ w ~ L/R: dψ w /dt =  ψ w /τ w Quadratic kink: γ  Γ [1d c /d] = 0 coupled to slow flux diffusion γψ w =  ψ w /τ w : τ w >> τ Alfvén Cubic Dispersion Relation with new slow root the RWM: γ  Γ [1(d c /d) γτ w /(γτ w + 1)] = 0
14 KINK MODE GROWTH IS SLOWED BY RESISTIVE WALL 0 = ( γ τ γ Γ 1 d w ) c d γ τ w + 1 } Ideal Stability } Resistive Wall γ / Γ Real ω 0 γ τ w 1 Resistive Wall Mode ideal mode unstable PlasmaWall Separation, d/d c Resistive wall mode (RWM) is unstable Mode structure similar to ideal external kink Mode grows slowly: γ ~ τ 1 w /GAN/rs
15 RWM STABILIZED IN DIIID BY ROTATION FOR MANY WALLTIMES, τ W Normalized plasma pressure, β N, exceeds nowall stability limit by up to 40% n = 1 mode grows (γ ~ 1/τ W ) after toroidal rotation at q = 3 surface has decreased below ~1 khz /GAN/rs
16 ROTATION AND DISSIPATION CAN STABILIZE RWM Rotation Doppler shift: γ γ + iω where Ω is plasma rotation. Dissipation represented by friction loss (γ + iω)ν, where form of ν still being actively studied by theory community: (γ + iω)  Γ [1(d c /d) γτ w /(γτ w + 1)] + (γ + iω)ν = 0 (as shown in Chu, et al. Phys. Plasma 1995; consistent with numerical result of Bondeson & Ward, PRL 1994) Cubic Dispersion Relation with three roots: in region where d < d c new slow RWM root can be damped with fast stable kink mode roots tied to rotating plasma with usual ordering: τ w 1 << Ω << v Alfvén /L Why is RWM Slow Root Stabilized? kink energy release < dissipation loss of RWM slowed by wall in flowing plasma
17 γ / Γ KINK MODE GROWTH IS SLOWED BY RESISTIVE WALL AND STABILIZED BY PLASMA ROTATION (γ + iω) Γ 0 = + } Ideal Stability Stable Gap ω τ w 1 Resistive Wall Mode Plasma Mode γ Γ PlasmaWall Separation, d/d c Γ (d c /d)γ τ w γ τ w + 1 } Resistive Wall + (γ + iω) ν DIS } Plasma Dissipation Resistive wall mode (RWM) is unstable Mode structure similar to ideal external kink Mode grows slowly: γ ~ τ 1 w Dissipation + rotation stabilizes RWM Mode nearly stationary: ω ~ τw 1 << Ω plasma /GAN/rs
18 SUSTAINED ROTATION ABOVE CRITICAL VALUE RELIABLE OPERATION ABOVE THE NOWALL LIMIT β N Feedback control of NBI power keeps β N below stability limit (107603) 1 no wall β N (.4l i) 0 1 Rotation (khz) at q~ Time (ms) No other large scale instabilities encountered (NTM, n= RWM,... ) Ideal n=1 kink observed at the wallstabilized β limit Toroidal Angle δb p β N ~ β nowall N β = 3.7% τ g ~ 300 µs << τ wall DIII D NATIONAL FUSION FACILITY SAN DIEGO Time (ms) T rot ~1 ms < τ wall 58 0/EJS/wj
19 MARS PREDICTIONS OF Ω crit τ A IN QUALITATIVE AGREEMENT WITH MEASUREMENTS ON DIIID AND JET sound wave In DIIID Ω crit τ A ~ 0.0 with weak β dependence In JET Ω crit τ A ~ with weak β dependence Both damping models predict Ω crit within a factor of
20 MODE FREQUENCY AND DAMPING CANNOT BE FIT SIMULTANEOUSLY Growth rate γ RWM τ W experiment(ωτ ~0.0) A kinetic sound wave (κ = 0.5) Mode rotation frequency ω RWM τ W Both damping models predict γ too low RWM Kinetic damping predicts mode frequency ω RWM Further work on damping [e.g. neoclassical viscosity] models being explored DIII D NATIONAL FUSION FACILITY S A N D I E G O C β
21 NSTX provides crucial data for understanding the dissipation mechanisms that allow rotational stabilization of the RWM Insight from driftkinetic theory: Trappedparticle effects at finite ε significantly weaken ion Landau damping, but Toroidal inertia enhancement modifies eigenfunction when Ω φ / ω A > 1/4q (Columbia Univ.) Experimental Ω crit / ω A suggests scaling ε / q why? Is dissipation localized to resonant surfaces, or more global? Addressing questions above w/ NSTX / DIIID similarity experiments, and hires CHERS ST has uniquely high ω sound / ω A distinguish between ω s and ω A scaling NSTX DIIID shifted & scaled 1.1 Needed for predicting control requirements for RWM stabilization in ITER & CTF 13
22 FEEDBACK LOGIC FOR RWM FEEDBACK STABILIZATION Smart Shell Explicit Mode Control Feedback cancels the radial flux from MHD mode at wall sensor Feedback cancels the flux from MHD mode at plasma surface /GAN/rs
23 DIII D INTERNAL CONTROL COILS ARE PREDICTED TO PROVIDE STABILITY AT HIGHER BETA Inside vacuum vessel: Faster time response for feedback control Closer to plasma: more efficient coupling Internal Coils (Icoils) /GAN/rs
24 FEEDBACK WITH ICOILS IN DIIID INCREASES STABLE PLASMA PRESSURE TO NEAR IDEALWALL LIMIT VALEN code prediction Normalized Growth Rate γτ w No Feedback Ideal kink VALEN code:  DCON MHD stability  3D geometry of vacuum vessel and coil geometry Resistive Wall Mode: Open loop growth rate τ w is the vacuum vessel flux diffusion time (~ 3.5 ms) 0 0. NoWall Limit 0.4 C β IdealWall Limit DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
25 FEEDBACK WITH ICOILS IN DIIID INCREASES STABLE PLASMA PRESSURE TO NEAR IDEALWALL LIMIT Ccoil stabilizes slowly growing RWMs Normalized Growth Rate γτ w NoWall Limit No Feedback External Ccoils Accessible with External Ccoils 0.4 C β 0.6 Ideal kink IdealWall Limit External CCoil:  Control fields must penetrate wall  Induced eddy currents reduce feedback τ w is the vacuum vessel flux diffusion time (~3.5 ms) DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
26 Icoil stabilizes RWMs with growth rate 10 times faster than Ccoils Normalized Growth Rate γτ w FEEDBACK WITH ICOILS IN DIIID INCREASES STABLE PLASMA PRESSURE TO NEAR IDEALWALL LIMIT NoWall Limit No Feedback External Ccoils Internal Icoils Accessible with External Ccoils 0.4 C β 0.6 Accessible with Internal Icoils Ideal kink IdealWall Limit Internal ICoils:  Improved coil/plasma coupling  Improved spatial match to RWM field structure τ w is the vacuum vessel flux diffusion time (~3.5 ms) DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
27 FEEDBACK EFFICACY DEMONSTRATED BY GATING OFF THE GAIN FOR 0 MS AT TIME OF EXPECTED RWM ONSET (gauss) Feedback Gain β N n=1 δb r Time (ms) Without feedback, slow Ip ramp rate (0.5 MA/s) destabilizes slowly growing RWM With feedback, beta collapse avoided (cm) 1 0 Relative Displacement (SXR) n=1 mode starts up during feedback off period, stabilized after feedback is turned back on (ka) Feedback Current (C79) Feedback OFF 1530 Time (ms) n=1 mode detected on poloidal field probes and SXR arrays, decoupled from driver coils DIII D NATIONAL FUSION FACILITY S A N D I E G O
28 FEEDBACK WITH INTERNAL CONTROL COILS HAS ACHIEVED HIGH C β AT ROTATION BELOW CRITICAL LEVEL PREDICTED BY MARS Trajectories of plasma discharge in rotation versus C β No feedback plasma approaches limit and disrupts ideal wall limit C β Ccoil feedback plasma crosses limit & reaches higher pressure no wall limit 1.0 Unstable (without feedback) CCOIL MARS prediction Stable (without feedback) NO FEEDBACK time Rotation (km/s) DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
29 FEEDBACK WITH INTERNAL CONTROL COILS HAS ACHIEVED HIGH C β AT ROTATION BELOW CRITICAL LEVEL PREDICTED BY MARS With near zero Rotation, Cβ is near the maximum set by existing control system characteristics: bandwidth & processing time delay ideal wall 1.0 limit Icoil feedback plasma reaches near zero rotation C β Unstable MARS prediction Stable (without feedback) MARS /VALEN prediction with measured amplifier time response for zero rotation no wall limit ICOIL ZERO ROTATION CCOIL NO FEEDBACK time Rotation (km/s) DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
30 FEEDBACK WITH INTERNAL CONTROL COILS HAS ACHIEVED HIGH C β AT ROTATION BELOW CRITICAL LEVEL PREDICTED BY MARS Combination of low rotation and feedback reaches C β is the ideal walllimits ideal wall limit 1.0 Unstable ICOIL MARS prediction Stable (without feedback) C β MARS /VALEN prediction with measured power supply time response for zero rotation no wall limit ICOIL ZERO ROTATION CCOIL NO FEEDBACK time Rotation (km/s) DIII D NATIONAL FUSION FACILITY S A N D I E G O 6904/MO/jy
31 RWM FEEDBACK ASSISTS IN EXTENDING β n ~4 ADVANCED TOKAMAK DISCHARGE MORE THAN 1 SECOND 4.0 βn Feedback current (ka) Plasma Rotation (km/s) n=1 δb p Mode Amplitude (gauss) 0.0 F.B on No Feedback No Feedback With Feedback Estimated nowall limit / Feedback coil current amplitude With Feedback Time (ms) DIII D NATIONAL FUSION FACILITY S A N D I E G O High performance plasma approaches β ~ 6% Without feedback plasma disrupts due to RWM 6904/MO/jy
32 RWM Stabilization Has Opened New High Performance Regimes Above the NoWall Stability Limit Simultaneous feedback control of error fields and RWM Additional ECCD power in FY06 will help sustain high q min New divertor will help density control at high triangularity β T (%) β N 6l i 4l i Time (ms) Pressure (10 5 Pa) J (A/cm ) Safety Factor ρ DIII D NATIONAL FUSION FACILITY /EJS/rs
33 Applying Internal RWM Feedback Coils to the Port Plugs in ITER Increases β limit for n = 1 from β N =.5 to ~ 4 RWM Coil Concept for ITER VALEN Analysis Columbia University Baseline RWM coils located outside TF coils Internal RWM coils would be located inside Nowall limit the vacuum vessel behind shield module 7 RWM Coils mounted behind the BSM in but inside the vacuum vessel on the every other port except NBI ports. removable port plugs. (assumes 9 ms time constant for each BSM) Integration and Engineering feasibility of internal RWM coils is under study.
34 NCSX Compact Stellarator Lown Stability Stellarators provide external magnetic field transform aiming at: Steady state without current drive. Kink stable at sufficiently high pressure (β > 4%) without feedback control or rotation drive. Compact Stellarators (CS) improve on previous designs. Magnetic quasisymmetry: good confinement. link to tokamak physics. Lower aspect ratio. 3Period NCSX Plasma and Coil Design
35 NCSX Stability Modeling Predicts Kink Stability up to 6% PIES FreeBoundary Equilibrium at β = 4.1%
36 W7AS: β 3.4 % : Quiescent, Quasistationary (100 m3) <!> (%) Power (MW) (A.U.) <!> 540 ne Mirnov Ḃ P NB 1 P rad Time (s) MCZ B = 0.9 T, iota vac 0.5 Almost quiescent high β phase, MHDactivity in early mediumβ phase In general, β not limited by any detected MHDactivity. I P = 0, but there can be local currents Similar to High Density Hmode (HDH) Similar β>3.4% plasmas achieved with B = T with either NBIalone, or combined NBI + OXB ECH heating. Much higher than predicted β limit ~ %
37 Currentcarrying Systems are Subject to Reconnection Tearing Modes Normal magnetic shear Safety Factor 6 4 MSE data 3/ Reverse magnetic shear Minor radius (r/a) 1.0 A rational field line can be an O point around which islands form. ( j for normal shear, + j for reverse shear)
38 Pressuredriven Bootstrap Current is a Boon and a Bane  In the presence of a pressure gradient, trapped particles entrain a parallel bootstrap current. A neoclassical effect, i.e. collisional, but including nonlocal orbit effects.  May allow steadystate operation of axisymmetric toroidal systems.  Drives neoclassical tearing modes in normal shear regions due to current depletion in the magnetic islands. µ 0 dw 1.! nc dt = #" + a L 1$ 1 q % & L p ' ) ( w w + w c *.,  a &i % & g($) ' + w 3 ) ( L q L p *, + Ohmic current Bootstrap current Polarization current Finite transport correction
39 Theory Accurately Predicts Growth of Neoclassical Tearing Modes (NTM) W (cm) 5 R = 3m, T e ~ 5keV Magnetic 4 3 Theory ECE 1 4MW NBI Time (s) w (cm) R = 1m, T e ~ 1keV time (s)! p(meas) Shot Measured Island Width (cm) 0. 0 Island Width Predicted by Neoclassical Theory (cm) ! p(meas) Bootstrap current + normal shear drives NTM s.  Agrees to factor of ~ with neoclassical resistivity, over a wide range of plasma parameters.  Important challenge to theory of magnetic reconnection.  Reverse shear stabilizes NTM s, as predicted.  Strong implications for toroidal system optimization.
40 Replacing Bootstrap Current in Islands Stabilizes Neoclassical Tearing Modes ECCD Steerable Electron Cyclotron Current Drive wave launcher. ITER will have ECCD for NTM control.
41 DIII D Demonstrates NTM Active Stabilization with ECCD P NB (MW) Current 10 (MA) P NB (MW) ~ B (n = 1) (G) EC Power (MW) High beta is achieved with preemptive stabilization of the /1 NTM Stable operation at the nowall beta limit for >1 s Div. D α (au) 4 l i β N ECCD is applied before the mode appears Realtime tracking of the q= surface maintains current drive alignment Tearing mode appears promptly when ECCD is removed B (T) Time (ms) DIII D NATIONAL FUSION FACILITY
42 ECCD in ITER Can Reduce the m/n=/1 NTM Island Crossmachine bench marking... R.J. La Haye, et.al., submitted to Nuclear Fusion Locking condition from 0D model w 3 w ω 0 τ A0 a (1 + 0 a)= * 14 1 τ w τ E0 Island growth rate (τ R /r) dw/dt ITER, m/n=/1, β N = 1.84 NO ECCD Unstable Region 1 MW ECCD No Modulation (K 1 = 0.38, F=1) NO ECCD Saturated Island (if Beta Maintained and if Mode Does Not Lock) m/n=/1 Island full width w (cm) 1 MW ECCD 50/50 Modulation (K 1 = 0.74, F = 0.5) DIII D ITER...τ w = ms (J. Bialek)...f 0 = khz (A. Polevoi)...τ E0 = s (J. Cordey)...τ A0 = μs (Y. Gribov)... w = a lock w 5 cm in ITER to lock w 10 cm at f 0 = 1.4 khz 5305/RJL/jy
43 Key Open Issues in Stability Advanced Tokamak Spherical Torus Lown Kink: Rotation Stabilization Physics & Scaling Scale Active Feedback to ITER  n = 1,, Coil Modularity & Failure of Mode Rigidity Lown Tearing: NTM Active Control Requirements for ITER Quantitative Theory: Seeding physics, island rotation, ECCD localization & modulation, small island modeling Compact Stellarator Lown Kink: Validate nowall highbeta kink limits Rotation effects in QS equilibria Lown Tearing: NTM control with external magnetic transform + large bootstrap current Magnetic Island control as β and Ip vary.
Analysis and modelling of MHD instabilities in DIIID plasmas for the ITER mission
Analysis and modelling of MHD instabilities in DIIID plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. PazSoldan 2, F. Carpanese 3, C.C. Petty 2, T.C.
More informationExtended Lumped Parameter Model of Resistive Wall Mode and The Effective SelfInductance
Extended Lumped Parameter Model of Resistive Wall Mode and The Effective SelfInductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.
More informationSTABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK
GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This
More informationEffects of stellarator transform on sawtooth oscillations in CTH. Jeffrey Herfindal
Effects of stellarator transform on sawtooth oscillations in CTH Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, E.C. Howell, C.A. Johnson, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A.
More informationDIII D Research in Support of ITER
Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 1318, 28 DIIID Research Has Made Significant Contributions in the Design
More informationNeoclassical Tearing Modes
Neoclassical Tearing Modes O. Sauter 1, H. Zohm 2 1 CRPPEPFL, Lausanne, Switzerland 2 MaxPlanckInstitut für Plasmaphysik, Garching, Germany Physics of ITER DPG Advanced Physics School 2226 Sept, 2014,
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 informationThe RFP: Plasma Confinement with a Reversed Twist
The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of WisconsinMadison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed
More informationGA A26887 ADVANCES TOWARD QHMODE VIABILITY FOR ELMFREE OPERATION IN ITER
GA A26887 ADVANCES TOWARD QHMODE VIABILITY FOR ELMFREE OPERATION IN ITER by A.M. GAROFALO, K.H. BURRELL, M.J. LANCTOT, H. REIMERDES, W.M. SOLOMON and L. SCHMITZ OCTOBER 2010 DISCLAIMER This report was
More 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 informationSupported by. Role of plasma edge in global stability and control*
NSTX Supported by College W&M Colorado Sch Mines Columbia U CompX General Atomics INL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U
More informationOverview of Pilot Plant Studies
Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology
More informationCharacterization of neoclassical tearing modes in highperformance I mode plasmas with ICRF mode conversion flow drive on Alcator CMod
1 EX/P422 Characterization of neoclassical tearing modes in highperformance I mode plasmas with ICRF mode conversion flow drive on Alcator CMod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.
More informationDirect drive by cyclotron heating can explain spontaneous rotation in tokamaks
Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.J. Zheng Institute for Fusion Studies University of Texas at Austin 12th USEU Transport Task Force Annual
More informationTokamak/Helical Configurations Related to LHD and CHSqa
9TH WORKSHOP ON MHD STABILITY CONTROL: "CONTROL OF MHD STABILITY: BACK TO THE BASICS" NOVEMBER 2123, 2004, PRINCETON PLASMA PHYSICS LABORATORY Tokamak/Helical Configurations Related to LHD and CHSqa
More informationThe Advanced Tokamak: Goals, prospects and research opportunities
The Advanced Tokamak: Goals, prospects and research opportunities Amanda Hubbard MIT Plasma Science and Fusion Center with thanks to many contributors, including A. Garafolo, C. Greenfield, C. Kessel,
More informationIntroduction to Fusion Physics
Introduction to Fusion Physics Hartmut Zohm MaxPlanckInstitut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction
More informationELM Suppression in DIIID Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations
1 EXC/P502 ELM Suppression in DIIID Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science
More informationNonsolenoidal Startup and Plasma Stability at NearUnity Aspect Ratio in the Pegasus Toroidal Experiment
1 EXS/P207 Nonsolenoidal Startup and Plasma Stability at NearUnity Aspect Ratio in the Pegasus Toroidal Experiment R.J. Fonck 1), D.J. Battaglia 2), M.W. Bongard 1), E.T. Hinson 1), A.J. Redd 1), D.J.
More informationGA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME
GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME by R. NAZIKIAN, M.E. AUSTIN, R.V. BUDNY, M.S. CHU, W.W. HEIDBRINK, M.A. MAKOWSKI, C.C. PETTY, P.A. POLITZER, W.M. SOLOMON, M.A.
More informationThe FieldReversed Configuration (FRC) is a highbeta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is
and Stability of FieldReversed Equilibrium with Toroidal Field Configurations Atomics General Box 85608, San Diego, California 921865608 P.O. APS Annual APS Meeting of the Division of Plasma Physics
More informationStability Properties of Toroidal Alfvén Modes Driven. N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye
Stability Properties of Toroidal Alfvén Modes Driven by Fast Particles Λ N. N. Gorelenkov, S. Bernabei, C. Z. Cheng, K. Hill, R. Nazikian, S. Kaye Princeton Plasma Physics Laboratory, P.O. Box 451, Princeton,
More informationEvaluation of CT injection to RFP for performance improvement and reconnection studies
Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi
More informationModeling of active control of external magnetohydrodynamic instabilities*
PHYSICS OF PLASMAS VOLUME 8, NUMBER 5 MAY 2001 Modeling of active control of external magnetohydrodynamic instabilities* James Bialek, Allen H. Boozer, M. E. Mauel, and G. A. Navratil Department of Applied
More informationResearch of Basic Plasma Physics Toward Nuclear Fusion in LHD
Research of Basic Plasma Physics Toward Nuclear Fusion in LHD Akio KOMORI and LHD experiment group National Institute for Fusion Science, Toki, Gifu 5095292, Japan (Received 4 January 2010 / Accepted
More informationToroidal confinement of nonneutral plasma. Martin Droba
Toroidal confinement of nonneutral plasma Martin Droba Contents Experiments with toroidal nonneutral plasma Magnetic surfaces CNT and IAPhigh current ring Conclusion 2. Experiments with toroidal nonneutral
More informationActive and Fast Particle Driven Alfvén Eigenmodes in Alcator CMod
Active and Fast Particle Driven Alfvén Eigenmodes in Alcator CMod 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 informationStellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK
Stellarators Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 6 th February 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously... Toroidal devices
More informationModelling of the penetration process of externally applied helical magnetic perturbation of the DED on the TEXTOR tokamak
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 8 (6) 69 8 PLASMA PHYSICS AND CONTROLLED FUSION doi:.88/7/8// Modelling of the penetration process of externally applied helical magnetic perturbation
More informationMeasuring from electron temperature fluctuations in the Tokamak Fusion Test Reactor
PHYSICS OF PLASMAS VOLUME 5, NUMBER FEBRUARY 1998 Measuring from electron temperature fluctuations in the Tokamak Fusion Test Reactor C. Ren, a) J. D. Callen, T. A. Gianakon, and C. C. Hegna University
More informationarxiv: v1 [physics.plasmph] 11 Mar 2016
1 Effect of magnetic perturbations on the 3D MHD selforganization of shaped tokamak plasmas arxiv:1603.03572v1 [physics.plasmph] 11 Mar 2016 D. Bonfiglio 1, S. Cappello 1, M. Veranda 1, L. Chacón 2 and
More informationControl of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain
Control of resistive wall modes in a cylindrical tokamak with plasma rotation and complex gain arxiv:146.5245v1 [physics.plasmph] 2 Jun 214 D. P. Brennan and J. M. Finn June 23, 214 Department of Astrophysical
More informationMHD instability driven by suprathermal electrons in TJII stellarator
MHD instability driven by suprathermal electrons in TJII stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. JiménezGómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov
More informationImpact of EnergeticIonDriven Global Modes on Toroidal Plasma Confinements
Impact of EnergeticIonDriven Global Modes on Toroidal Plasma Confinements Kazuo TOI CHS & LHD Experimental Group National Institute for Fusion Science Toki 595292, Japan Special contributions from:
More informationSMR/ Summer College on Plasma Physics. 30 July  24 August, Introduction to Magnetic Island Theory.
SMR/18561 2007 Summer College on Plasma Physics 30 July  24 August, 2007 Introduction to Magnetic Island Theory. R. Fitzpatrick Inst. for Fusion Studies University of Texas at Austin USA Introduction
More informationGA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIIID
GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIIID by C.C. PETTY, P.A. POLITZER, R.J. JAYAKUMAR, T.C. LUCE, M.R. WADE, M.E. AUSTIN, D.P. BRENNAN, T.A. CASPER, M.S. CHU, J.C. DeBOO, E.J. DOYLE,
More informationEFFECT OF EDGE NEUTRAL SOUCE PROFILE ON HMODE PEDESTAL HEIGHT AND ELM SIZE
EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON HMODE 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 DIIID Group 47 th Annual Meeting
More informationHeat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UWMadison
Heat Transport in a Stochastic Magnetic Field John Sarff Physics Dept, UWMadison CMPD & CMSO Winter School UCLA Jan 510, 2009 Magnetic perturbations can destroy the nestedsurface topology desired for
More informationComparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIIID Tokamak
Comparison of Pellet Injection Measurements with a Pellet Cloud Drift Model on the DIIID Tokamak T.C. Jernigan, L.R. Baylor, S.K. Combs, W.A. Houlberg (Oak Ridge National Laboratory) P.B. Parks (General
More informationPhase ramping and modulation of reflectometer signals
4th Intl. Reflectometry Workshop  IRW4, Cadarache, March 22nd  24th 1999 1 Phase ramping and modulation of reflectometer signals G.D.Conway, D.V.Bartlett, P.E.Stott JET Joint Undertaking, Abingdon, Oxon,
More informationStellarators and the path from ITER to DEMO
Stellarators and the path from ITER to DEMO Allen H. Boozer Department of Applied Physics and Applied Mathematics Columbia University, New York, NY 10027 (Dated: May 26, 2008) A demonstration of fusion
More informationSaturated ideal modes in advanced tokamak regimes in MAST
Saturated ideal modes in advanced tokamak regimes in MAST IT Chapman 1, MD Hua 1,2, SD Pinches 1, RJ Akers 1, AR Field 1, JP Graves 3, RJ Hastie 1, CA Michael 1 and the MAST Team 1 EURATOM/CCFE Fusion
More informationCurrent density modelling in JET and JT60U identity plasma experiments. Paula Sirén
Current density modelling in JET and JT60U identity plasma experiments Paula Sirén 1/12 1/16 EuratomTEKES EuratomTekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET
More informationq(0) pressure after crash 1.0 Single tearing on q=2 Double tearing on q=2 0.5
EX/P1 MHD issues in Tore Supra steadystate fully noninductive scenario P Maget 1), F Imbeaux 1), G Giruzzi 1), V S Udintsev ), G T A Huysmans 1), H Lütjens 3), JL Ségui 1), M Goniche 1), Ph Moreau
More informationGA A23736 EFFECTS OF CROSSSECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT
GA A3736 EFFECTS OF CROSSSECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT by T.C. LUCE, C.C. PETTY, and J.E. KINSEY AUGUST DISCLAIMER This report was prepared as an account of work sponsored by an
More informationELM control with RMP: plasma response models and the role of edge peeling response
ELM control with RMP: plasma response models and the role of edge peeling response Yueqiang Liu 1,2,3,*, C.J. Ham 1, A. Kirk 1, Li Li 4,5,6, A. Loarte 7, D.A. Ryan 8,1, Youwen Sun 9, W. Suttrop 10, Xu
More informationFast Secondary Reconnection and the Sawtooth Crash
Fast Secondary Reconnection and the Sawtooth Crash Maurizio Ottaviani 1, Daniele Del Sarto 2 1 CEAIRFM, SaintPaullezDurance (France) 2 Université de Lorraine, Institut Jean Lamour UMRCNRS 7198, Nancy
More informationMultimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER
1 IT/P68 Multimachine Extrapolation of Neoclassical Tearing Mode Physics to ITER R. J. Buttery 1), S. Gerhardt ), A. Isayama 3), R. J. La Haye 4), E. J. Strait 4), D. P. Brennan 5), P. Buratti 6), D.
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 informationMacroscopic Stability of High β N MAST Plasmas
1 EXS/P54 Macroscopic Stability of High β N MAST Plasmas I.T. Chapman 1), R.J. Akers 1), L.C. Appel 1), N.C. Barratt 2), M.F. de Bock 1,7), A.R. Field 1), K.J. Gibson 2), M.P. Gryaznevich 1), R.J. Hastie
More informationQTYUIOP 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 informationAdvancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment
Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,
More informationThe Magnetorotational Instability
The Magnetorotational Instability Nick Murphy HarvardSmithsonian Center for Astrophysics Astronomy 253: Plasma Astrophysics March 10, 2014 These slides are based off of Balbus & Hawley (1991), Hawley
More informationSignificance of MHD Effects in Stellarator Confinement
Significance of MHD Effects in Stellarator Confinement A. Weller 1, S. Sakakibara 2, K.Y. Watanabe 2, K. Toi 2, J. Geiger 1, M.C. Zarnstorff 3, S.R. Hudson 3, A. Reiman 3, A. Werner 1, C. Nührenberg 1,
More informationNonlinear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.
Nonlinear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations. M. Becoulet 1, F. Orain 1, G.T.A. Huijsmans 2, P. Maget 1, N. Mellet 1, G. DifPradalier 1, G. Latu 1, C. Passeron
More informationGA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D
GA A271 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D by C.C. PETTY, J.S. degrassie, R.W. HARVEY, Y.R. LINLIU, J.M. LOHR, T.C. LUCE, M.A. MAKOWSKI, Y.A. OMELCHENKO, and R. PRATER AUGUST 2001 DISCLAIMER This
More informationIntegrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport
1 Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama Japan Atomic Energy Agency, Naka, Ibarakiken, 3110193 Japan
More informationW.M. Solomon 1. Presented at the 54th Annual Meeting of the APS Division of Plasma Physics Providence, RI October 29November 2, 2012
Impact of Torque and Rotation in High Fusion Performance Plasmas by W.M. Solomon 1 K.H. Burrell 2, R.J. Buttery 2, J.S.deGrassie 2, E.J. Doyle 3, A.M. Garofalo 2, G.L. Jackson 2, T.C. Luce 2, C.C. Petty
More informationTokamak 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 informationCMod Core Transport Program. Presented by Martin Greenwald CMod PAC Feb. 68, 2008 MIT Plasma Science & Fusion Center
CMod Core Transport Program Presented by Martin Greenwald CMod PAC Feb. 68, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly
More informationD 3 He HA tokamak device for experiments and power generations
D He HA tokamak device for experiments and power generations USJapan Fusion Power Plant Studies Contents University of Tokyo, Japan January , 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,
More informationCHAPTER 8 PERFORMANCELIMITING MAGNETOHYDRODYNAMICS IN JET
CHAPTER 8 PERFORMANCELIMITING MAGNETOHYDRODYNAMICS IN JET R. J. BUTTERY* and T. C. HENDER EURATOM0UKAEA Fusion Association, Culham Science Centre Abingdon, Oxfordshire OX14 3DB, United Kingdom Received
More informationAnalytical Study of RWM Feedback Stabilisation with Application to ITER
CT/P Analytical Study of RWM Feedback Stabilisation with Application to ITER Y Gribov ), VD Pustovitov ) ) ITER International Team, ITER Naka Joint Work Site, Japan ) Nuclear Fusion Institute, Russian
More informationSimulations of Sawteeth in CTH. Nicholas Roberds August 15, 2015
Simulations of Sawteeth in CTH Nicholas Roberds August 15, 2015 Outline Problem Description Simulations of a small tokamak Simulations of CTH 2 Sawtoothing Sawtoothing is a phenomenon that is seen in all
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 information1 EX/P59 International Stellarator/Heliotron Database Activities on HighBeta Confinement and Operational Boundaries
1 International Stellarator/Heliotron Database Activities on HighBeta Confinement and Operational Boundaries A. Weller 1), K.Y. Watanabe 2), S. Sakakibara 2), A. Dinklage 1), H. Funaba 2), J. Geiger 1),
More informationarxiv: v2 [physics.plasmph] 24 Jul 2017
Rotation and Neoclassical Ripple Transport in ITER E. J. Paul Department of Physics, University of Maryland, College Park, MD 20742, USA arxiv:1703.06129v2 [physics.plasmph] 24 Jul 2017 M. Landreman Institute
More informationPROGRESS IN STEADYSTATE SCENARIO DEVELOPMENT IN THE DIIID TOKAMAK
PROGRESS IN STEADYSTATE SCENARIO DEVELOPMENT IN THE DIIID TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared
More informationInitial Experimental Program Plan for HSX
Initial Experimental Program Plan for HSX D.T. Anderson, A F. Almagri, F.S.B. Anderson, J. Chen, S. Gerhardt, V. Sakaguchi, J. Shafii and J.N. Talmadge, UWMadison HSX Plasma Laboratory Team The Helically
More informationSawtooth Control. J. P. Graves CRPP, EPFL, Switzerland. FOM Instituut voor Plasmafysica Rijnhuizen, Association EURATOMFOM, The Netherlands
Sawtooth Control J. P. Graves CRPP, EPFL, Switzerland B. Alper 1, I. Chapman 2, S. Coda, M. de Baar 3, L.G. Eriksson 4, R. Felton 1, D. Howell 2, T. Johnson 5, V. Kiptily 1, R. Koslowski 6, M. Lennholm
More informationDT Fusion Power Production in ELMfree Hmodes in JET
JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELMfree Hmodes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may
More informationLinjin Zheng, Infernal Modes at Tokamak H mode Pedestal A Physics Interpreta;on for Edge Harmonic Oscilla;on (EHO)
International Sherwood Fusion Theory Conference, Austin, May 24, 2011 Infernal Modes at Tokamak H mode Pedestal A Physics Interpreta;on for Edge Harmonic Oscilla;on (EHO) Linjin Zheng, M. T. Kotschenreuther,
More informationAmplification of magnetic fields in core collapse
Amplification of magnetic fields in core collapse Miguel Àngel Aloy Torás, Pablo CerdáDurán, Thomas Janka, Ewald Müller, Martin Obergaulinger, Tomasz Rembiasz Universitat de València; MaxPlanckInstitut
More informationThe performance of improved Hmodes at ASDEX Upgrade and projection to ITER
EX/11 The performance of improved Hmodes at ASDEX Upgrade and projection to George Sips MPI für Plasmaphysik, EURATOMAssociation, D85748, Germany G. Tardini 1, C. Forest 2, O. Gruber 1, P. Mc Carthy
More informationPHYSICS DESIGN FOR ARIESCS
PHYSICS DESIGN FOR ARIESCS L. P. KU, a * P. R. GARABEDIAN, b J. LYON, c A. TURNBULL, d A. GROSSMAN, e T. K. MAU, e M. ZARNSTORFF, a and ARIES TEAM a Princeton Plasma Physics Laboratory, Princeton University,
More informationMagnetic Reconnection: explosions in space and astrophysical plasma. J. F. Drake University of Maryland
Magnetic Reconnection: explosions in space and astrophysical plasma J. F. Drake University of Maryland Magnetic Energy Dissipation in the Universe The conversion of magnetic energy to heat and high speed
More informationINITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS
INITIAL EVALUATION OF COMPUTATIONAL TOOLS FOR STABILITY OF COMPACT STELLARATOR REACTOR DESIGNS A.D. Turnbull and L.L. Lao General Atomics (with contributions from W.A. Cooper and R.G. Storer) Presentation
More informationObservation of tearing mode deceleration and locking due to eddy currents induced in a conducting shell
PHYSICS OF PLASMAS VOLUME 11, NUMBER 5 MAY 2004 Observation of tearing mode deceleration and locking due to eddy currents induced in a conducting shell B. E. Chapman Department of Physics, University of
More informationOn ElectronCyclotron Waves in Relativistic NonThermal Tokamak Plasmas
1 On ElectronCyclotron Waves in Relativistic NonThermal 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 informationNonlinear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade
1 TH/P126 Nonlinear modeling of the Edge Localized Mode control by Resonant Magnetic Perturbations in ASDEX Upgrade F.Orain 1, M.Hölzl 1, E.Viezzer 1, M.Dunne 1, M.Bécoulet 2, P.Cahyna 3, G.T.A.Huijsmans
More informationFusion Nuclear Science (FNS) Mission & High Priority Research
Fusion Nuclear Science (FNS) Mission & High Priority Research Topics Martin Peng, Aaron Sontag, Steffi Diem, John Canik, HM Park, M. Murakami, PJ Fogarty, Mike Cole ORNL 15 th International Spherical Torus
More informationTokamak operation at low q and scaling toward a fusion machine. R. Paccagnella^
Tokamak operation at low q and scaling toward a fusion machine R. Paccagnella^ Consorzio RFX, Associazione EuratomENEA sulla Fusione, Padova, Italy ^ and Istituto Gas Ionizzati del Consiglio Nazionale
More informationDIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT GENERATION TOKAMAKS
GA A25808 DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT GENERATION TOKAMAKS by D.A. HUMPHREYS, J.R. FERRON, A.W. HYATT, R.J. La HAYE, J.A. LEUER, B.G. PENAFLOR, M.L. WALKER, A.S. WELANDER,
More informationModel based optimization and estimation of the field map during the breakdown phase in the ITER tokamak
Model based optimization and estimation of the field map during the breakdown phase in the ITER tokamak Roberto Ambrosino 1 Gianmaria De Tommasi 2 Massimiliano Mattei 3 Alfredo Pironti 2 1 CREATE, Università
More informationComparison 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 informationThe EPED Pedestal Model: Extensions, Application to ELMSuppressed Regimes, and ITER Predictions
The EPED Pedestal Model: Extensions, Application to ELMSuppressed Regimes, and ITER Predictions P.B. Snyder 1, T.H. Osborne 1, M.N.A. Beurskens 2, K.H. Burrell 1, R.J. Groebner 1, J.W. Hughes 3, R. Maingi
More informationMHD Equilibrium and Stability of Tokamaks and RFP Systems with 3D Helical Cores
15th Workshop on MHD Stability Control, Madison, WI, USA, November 1517, 21 MHD Equilibrium and Stability of Tokamaks and FP Systems with 3D Helical Cores W. A. Cooper Ecole Polytechnique Fédérale de
More informationFlow dynamics and plasma heating of spheromaks in SSX
Flow dynamics and plasma heating of spheromaks in SSX M. R. Brown and C. D. Cothran, D. Cohen, J. Horwitz, and V. Chaplin Department of Physics and Astronomy Center for Magnetic Self Organization Swarthmore
More informationMST and the Reversed Field Pinch. John Sarff
MST and the Reversed Field Pinch John Sarff APAM Columbia University Sep 19, 2014 Outline Tutoriallevel review of tearing stability, magnetic relaxation, and transport in the RFP Ionrelated physics topics
More informationHOW THE DEMO FUSION REACTOR SHOULD LOOK IF ITER FAILS. Paul Garabedian and Geoffrey McFadden
HOW THE DEMO FUSION REACTOR SHOULD LOOK IF ITER FAILS Paul Garabedian and Geoffrey McFadden 1. Summary Runs of the NSTAB equilibrium and stability code show there are many 3D solutions of the advanced
More informationgeneralfusion Characterization of General Fusion's Plasma Devices 2015 Nimrod Summer Workshop
Characterization of General Fusion's Plasma Devices 2015 Nimrod Summer Workshop Aaron Froese, Charlson Kim, Meritt Reynolds, Sandra Barsky, Victoria Suponitsky, Stephen Howard, Russ Ivanov, Peter O'Shea,
More informationDEPENDENCE OF THE HMODE PEDESTAL STRUCTURE ON ASPECT RATIO
21 st IAEA Fusion Energy Conference Chengdu, China Oct. 1621, 2006 DEPENDENCE OF THE HMODE PEDESTAL STRUCTURE ON ASPECT RATIO R. Maingi 1, A. Kirk 2, T. Osborne 3, P. Snyder 3, S. Saarelma 2, R. Scannell
More informationICRH Experiments on the Spherical Tokamak GlobusM
1 Experiments on the Spherical Tokamak GlobusM V.K.Gusev 1), F.V.Chernyshev 1), V.V.Dyachenko 1), Yu.V.Petrov 1), N.V.Sakharov 1), O.N.Shcherbinin 1), V.L.Vdovin 2) 1) A.F.Ioffe PhysicoTechnical Institute,
More informationGeneralized Solovev equilibrium with sheared flow of arbitrary direction and stability consideration
Generalized Solovev equilibrium with sheared flow of arbitrary direction and stability consideration D.A. Kaltsas and G.N. Throumoulopoulos Department of Physics, University of Ioannina, GR 451 10 Ioannina,
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. GarciaMunoz M. A. Van Zeeland, S. Sharapov, Ph. Lauber, J. Ayllon, I. Classen, G. Conway, J. Ferreira,
More informationPer Helander. Contributions from: R. Kleiber, A. Mishchenko, J. Nührenberg, P. Xanthopoulos. Wendelsteinstraße 1, Greifswald
Rotation and zonal flows in stellarators Per Helander Wendelsteinstraße 1, 17491 Greifswald Contributions from: R. Kleiber, A. Mishchenko, J. Nührenberg, P. Xanthopoulos What is a stellarator? In a tokamak
More informationModels for Global Plasma Dynamics
Models for Global Plasma Dynamics F.L. Waelbroeck Institute for Fusion Studies, The University of Texas at Austin International ITER Summer School June 2010 Outline 1 Models for LongWavelength Plasma
More informationPresentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna, Austria Sept. 14, 2015
Review of Theory Papers at 14 th IAEA technical meeting on Engertic Particles in Magnetic Confinement systems Presentation by Herb Berk University of Texas at Austin Institute for Fusion Studies in Vienna,
More informationM. T. Beidler 1, J. D. Callen 1, C. C. Hegna 1, C. R. Sovinec 1, N. M. Ferraro 2
P1.015 Nonlinear Modeling Benchmarks of Forced Magnetic Reconnection with NIMROD and M3DC1 M. T. Beidler 1, J. D. Callen 1, C. C. Hegna 1, C. R. Sovinec 1, N. M. Ferraro 2 1 Department of Engineering
More informationPrinceton Plasma Physics Laboratory
Princeton Plasma Physics Laboratory PPPL4239 PPPL4239 Computation of Three Dimensional Tokamak and Spherical Torus Equilibria Jongkyu Park, Allen H. Boozer, and Alan H. Glasser (Preprint) May 27 Prepared
More information