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Presented by J.E. Menard Princeton Plasma Physics Laboratory MHD SFG Meeting Thursday, May 19, 2005 nearly identical to my talk at: 2005 International.

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Presentation on theme: "Presented by J.E. Menard Princeton Plasma Physics Laboratory MHD SFG Meeting Thursday, May 19, 2005 nearly identical to my talk at: 2005 International."— Presentation transcript:

1 Presented by J.E. Menard Princeton Plasma Physics Laboratory MHD SFG Meeting Thursday, May 19, 2005 nearly identical to my talk at: 2005 International Sherwood Fusion Theory Conference April 11-13, 2005 Stateline, Nevada, USA This work supported by the US DoE, UK EPSRC, and EURATOM Unique MHD Properties of Spherical Torus Plasmas Supported by

2 J.E. Menard – MHD SFG – 5/19/ Special thanks to contributors to this talk: J. Bialek, S.A. Sabbagh, A. Sontag, W. Zhu (Columbia University) M.S. Chu, R.J. La Haye, P.B. Snyder (General Atomics) D. Stutman, K. Tritz (Johns Hopkins University) A.H. Glasser, X.Z. Tang (Los Alamos National Laboratory) H. Strauss (New York University) R. Maingi, Y.-K.M. Peng (Oak Ridge National Laboratory) E. Belova, J. Breslau, E.D. Fredrickson, G. Fu, D.A. Gates, J. Manickam, S.S. Medley, M. Ono, W. Park (PPPL) W. Heidbrink (University of California – Irvine) R. Betti, L. Guazzotto (University of Rochester) T. Jarboe, R. Raman (University of Washington) R. Fonck, C. Hegna (University of Wisconsin – Madison) R. Buttery, S. Saarelma, A. Sykes, H.R. Wilson (Culham Science Centre – United Kingdom) Y. Ono, Y. Takase (University of Tokyo - Japan) and the entire NSTX Research Team Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics NYU ORNL PPPL PSI SNL UC Davis UC Irvine UCLA UCSD U Maryland U Rochester U Washington U Wisconsin Culham Sci Ctr Hiroshima U HIST Kyushu Tokai U Niigata U Tsukuba U U Tokyo JAERI Ioffe Inst TRINITI KBSI KAIST ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching U Quebec

3 J.E. Menard – MHD SFG – 5/19/ World Spherical Torus (ST) Community Continues to Grow in Experiments and Research Goals Lowered cost, very high , and low-A physics attract high interest HIST LATE NUCTE-ST TS3,4 TST-2 UTST All Japan ST SUNIST MAST Globus-M GUTTA Proto-Sphera STPC-EX KTM HIT-SI Pegasus CDX-U/LTX NSTX ETE 19 ST research centers world-wide (M. Peng – ORNL)

4 J.E. Menard – MHD SFG – 5/19/ NSTX (USA) and MAST (UK) are investigating low-collisionality toroidal plasmas at low aspect ratio NSTXMAST Close-fitting passive stabilizers:  Wall stabilization of external kink Internal poloidal field coils:  Plasma formation w/o solenoid Typical Parameters Aspect ratio A < 1.6 Elongation  < 2.7 Triangularity  < 0.8 Major radius R m Plasma Current I p < 1.5MA Toroidal Field B T0 < 0.6T Poloidal flux< 1Wb Pulse Length< 1.5s NBI Heating< 7MW T e, T i = 1-4keV n e = m -3  e, i  0.1, 1 S (Lundquist #) = 10 7 (core) Pr (Prandtl #) = R0R0 a

5 J.E. Menard – MHD SFG – 5/19/ Largest STs operate in unique MHD parameter regime Low–A configuration  access to high  –Configuration generates strong natural shaping –Higher stability limits with broad pressure and current profiles –Diamagnetic frequency comparable to ideal mode growth rates Neutral Beam Injection (NBI) heating dominant –Largest STs presently have uni-directional beam injection –Large toroidal rotation inseparable from high  –n, p profiles decoupled from flux surfaces –Flow-shearing rates comparable to ideal growth rates –Large population of energetic ions produced Fast ions constitute 15-50% of total stored energy V fast / V Alfvén = 2-4  strong drive for energetic particle modes Parameters potentially relevant for ITER fast-ion physics The ST is an unique & important platform for testing MHD theory and simulation

6 J.E. Menard – MHD SFG – 5/19/ ST configuration allows access to high  plasmas Troyon scaling  Max(  T ) ~  N I P / aB T Low A  higher I P / aB T at same q* (i.e. same kink stability) Low A also has higher  N limit w.r.t. kink & ballooning modes P EGASUS : Explore plasma limits as A  1 Paramagnetic plasma: local   50%, diamagnetic: local   100%

7 J.E. Menard – MHD SFG – 5/19/ STs can produce strongly-shaped plasmas Natural elongation increases rapidly with decreasing A and l i Low-l i plasma stability enhanced by large edge magnetic shear at low-A Elongation  up to 2.6 at  =0.5 achieved in NSTX at low l i = – NSTX will increase  from 0.5  0.8 at high  this year Low A needs high  and  to maximize  T at high  P  (i.e. bootstrap fraction) TRANSP  Up to 60% non-inductive current fraction w/ f BS = 50% at  T = 15-20% Internal Inductance  Higher  yields simultaneously higher  T and f BS  0.5  1/2  P  (elongation) Control system upgrade  higher  (D. Gates - PPPL)  T (%)  0.5  1/2  P

8 J.E. Menard – MHD SFG – 5/19/ Unidirectional beam-heating drives large toroidal rotation Ne()Ne() Model n e ( ,R) w/   matches n e data Includes fast-ion p and  nDnD at t=333ms Solid curves: Model n s ( ,R) w/ rotation Dashed curves: N s (  density w/o rotation M S = v  / v sound = , M A = v  / v A = (higher in ST) Force balance + neutrality  n e ( ,R) = N e (  ) exp(M  2 (  ) (R 2 –R 0 2 )/2T(  )) Centrifugal effects evident in n e (R) profiles:

9 J.E. Menard – MHD SFG – 5/19/ Presently studying role of flow in equilibrium reconstructions and effect of p-anisotropy FLOW code ( L. Guazzotto – U. Roch.) Density profile shift in a static plasma for varying anisotropy for an NSTX-like equilibrium EFIT w/ rotation + MSE (S. Sabbagh, CU) Phys. Plasmas, Vol. 11, No. 2, February Z(m) R(m) t=0.257s  iso-surface p iso-surface (no p-anisotropy) Developing stability code for arbitrary flow and 

10 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity ST MHD areas treated in this presentation: Internal kink mode Resistive Wall Mode (RWM) Edge Localized Modes (ELM) Neoclassical Tearing Modes (NTM) Alfvén Eigenmodes (*AE) Solenoid-free ST plasma formation

11 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~ Mode  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection and electron beam injection –Plasma merging/compression and PF-coil direct induction

12 J.E. Menard – MHD SFG – 5/19/ Sawteeth are rare in NSTX at high-  and with large rotation Neutron rate  ½ expected value during mode activity, but sometimes recovers Instead, 1/1 mode saturates - Why? degrades fast-ion confinement flattens core rotation profile (Submitted for publication in Nuc. Fus. – J. Menard )

13 J.E. Menard – MHD SFG – 5/19/ SXR data consistent w/ rapid growth  saturation 227ms 228ms229ms 230ms240ms270ms (USXR data from Stutman & Tritz - JHU) Island model  h fit to SXR SXR data (line-integrated)

14 J.E. Menard – MHD SFG – 5/19/ Sheared rotation is stabilizing, but mode flattens   profile M3D M3D resistive MHD code  Sheared rotation slows mode growth by factor of 2-3 Core   flattening observed in M3D and experiment even w/o complete reconnection Complete collapse of   profile and island locking  disruption W. Park - PPPL

15 J.E. Menard – MHD SFG – 5/19/ Larger B P / B  in ST enhances   damping from modes Neoclassical Toroidal Viscosity (NTV) good candidate to explain core rotation flattening (K.C. Shaing et al., Phys. Fluids 29 (1986) 521, also Lazzaro, Sabbagh, Zhu…) Larger B P / B  in ST  larger ratio of b r m,n / B 1/1 mode NTV needed to match   evolution diamonds  measured   lines  calculated   (Example shown: Coupled 1/1 + 2/1 modes at high-   NTV apparently explains   flattening from 1/1  Important to develop and include improved viscosity models in non-linear MHD simulations Torque balance  Damping Without NTV With NTV W. Zhu – Columbia Univ.

16 J.E. Menard – MHD SFG – 5/19/ Diamagnetic effects may contribute to saturation of the 1/1 mode at high  1/1 island displaces core  enhanced  p and q in reconnection region –Locally enhanced  *i and  *e stabilizing, higher shear destabilizing –Rogers and Zakharov: quasi-linear model with high-A, circular plasma, no rotation –Significant non-linear stabilization possible for ST parameters for range of q-shear High   increased  *i  A  i  A  i /a A = R 0 /a = aspect ratio  i = ion skin depth a = minor radius  Model predictions: -Mode stable for  0 < 0.5  *i -Low / high shear  no saturation -Shear s  allows saturated  0 / r q=1  0.5 similar to measured displacement MSE will allow q measurement this year Preliminary M3D result   * and   may synergistically contribute to saturation (W. Park) B. Rogers and L. Zakharov Phys. Plasmas 2 (9), September 1995  0 /  *i  0 / r q= 

17 J.E. Menard – MHD SFG – 5/19/ MHDCounter 2FuidsCo 2Fuids Saturation with hot spot pulled away from x-point Crash faster than MHD case M A =+-0.3 M A =-0.3M A =+0.3 Temperature

18 J.E. Menard – MHD SFG – 5/19/ Saturated 1/1 modes observed late in longest-duration discharges this year Sawteeth (?) 400ms 1/1 mode

19 J.E. Menard – MHD SFG – 5/19/ Rotation flattening from 1/1 observed, rotation decays gradually thereafter

20 J.E. Menard – MHD SFG – 5/19/ Plasma J-profile appears nearly time-invariant late in saturation phase. Preliminary MSE EFITs consistent with q(0) < 1

21 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection and electron beam injection –Plasma merging/compression and PF-coil direct induction

22 J.E. Menard – MHD SFG – 5/19/ Wall stabilization physics understanding is key to sustained plasma operation at maximum  High  t < 40%,  N = 6.8 reached NN lili  N /l i = wall stabilized Global MHD modes can lead to rotation damping,  collapse Physics of sustained stabilization is applicable to ITER Operation with  N /  N no-wall > 1.3 at highest  N for pulse >>  wall NN DCON WW t(s) n=1 (no-wall) n=1 (wall) wall stabilized EFIT core plasma rotation (x10 kHz) (S. Sabbagh, CU)

23 J.E. Menard – MHD SFG – 5/19/ ST research will improve our understanding of rotational stabilization of the RWM Drift Kinetic Theory: –Trapped-particle effects at finite  significantly weaken ion Landau damping –Toroidal inertia enhancement modifies eigenfunction when   /  A > 1 / 4q 2 Experimental  crit consistent with scaling   / q 2 – why? ST has higher  sound /  A  distinguish between  s and  A scaling? Is stabilizing dissipation localized to resonant surfaces, or more global? –Attempting to answer these questions w/ NSTX / DIII-D similarity experiments (R. La Haye – GA) (A. Sontag - CU)

24 J.E. Menard – MHD SFG – 5/19/ Growth rate [ 1/s ] Active control of RWM in ST geometry will complement research at higher aspect ratio  2   N = R Z  R 0 + aR 0 - a DCON R 0 + a R 0 - a  B  (arb) RWM eigenfunction strongly ballooning at high , low-A  outboard coils effective Like (present) ITER design, NSTX feedback system must deal with external mid- plane coils and nearby (blanket-like) passive plates VALEN code J. Bialek – CU S. Sabbagh – CU, A. Glasser - LANL (Equilibria used have  Nno-wall = 5.1;  Nwall = 6.9) Feedback stabilize RWM at C  = 68% without rotation

25 J.E. Menard – MHD SFG – 5/19/ MARS code calculations for NSTX indicate  plasma  0 destabilizing for RWM   0 increases  WALL for large  WALL Also apparent lowering of no-wall limit Ideal plasma Resistive Plasma   = 0   0 required for benchmarking/comparison to M3D - Studying interplay between resistivity and dissipation Will test Bondeson/Chu kinetic damping model in MARS for NSTX - Kinetic damping model applicable to low-A needed No-wall limit Ideal-wall limit Chalmers, GA, PPPL

26 J.E. Menard – MHD SFG – 5/19/ M3D simulations examining role of  plasma and rotation Perturbed Poloidal flux at Saturates at w/ collisional viscosity Resistive plasma / resistive wall mode (RPRWM) growth rate scaling: (H. Strauss - NYU)   e  e    e  WALL  e     RWM interacts w/ tearing / EM  -ballooning mode Wall Plasma similar to analytic scaling Finn 1995; Betti 1998 Better dissipation models needed

27 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection and electron beam injection –Plasma merging/compression and PF-coil direct induction

28 J.E. Menard – MHD SFG – 5/19/ (From P.B. Snyder - GA)  ELITE code Coupled peeling-kink and ballooning modes explain many features of Edge-Localized-Modes (ELMs) in H-mode pedestal

29 J.E. Menard – MHD SFG – 5/19/ A=2.5 Collisionality, triangularity, and aspect ratio impact ELM stability Aspect ratio varied via R scan at fixed B T, I P, a, shape Need to extend stability scans to lower A, include  0,  *, rotation… P.B. Snyder, et al., Plasma Phys. Control. Fusion 46 (2004) A131–A141

30 J.E. Menard – MHD SFG – 5/19/ Sheared rotation predicted to enhance ELM stability in ST Experimental profiles analyzed w/ ELITE Expt. marginal p ped  2 kPa - consistent with analysis  10% variation in threshold with n and equilibrium q surf  = m-nq surf Mode number n=6 p ped = 2kPa (From S. Saarelma, H.R. Wilson – Culham, UK) Sheared edge rotation stabilizing –High-n modes most easily stabilized –10-20% increase in stable p ped depending on n-number and rotation Expt. v ped

31 J.E. Menard – MHD SFG – 5/19/ Model of ELM cycle including sheared rotation: 4. Hyper-exponential growth as dv/dr  0  ELM crash 1.  p < sheared-velocity limit  stable 2.  p > sheared-velocity limit  unstable 3. Instability reduces rotation shear Extension of Cowley / Wilson non-linear ballooning model to include rotation Filament-like structure A. Kirk, et al., PRL, June 2004

32 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection and electron beam injection –Plasma merging/compression and PF-coil direct induction

33 3/2 NTM used to study stabilizing role of curvature From R. J. Buttery, et al. PRL 88, 25 March 2002, p (Culham - UK) 2941 At higher  p get 2/1 NTM: – earlier excitations do not grow – usually requires H mode and high  p Sawteeth briefly reduce  p high enough  p  3/2 NTM 3/2 mode reduces energy confinement time: –  W  3.0kJ (11%) Chang & Callen ‘belt’ model predicts:  W  2.4kJ MAST Discharge

34 incomplete pressure flattening  w>~w d bootstrap term (drive) requires low collisionality ion polarisation effects  w>w pol “classical” resistive tearing index (assumed stabilizing) Stabilization terms require minimum island size Evolution described by modified Rutherford Eqn. field curvature  shape and aspect ratio dependence Ratio a GGJ / a bs   3/2  important as   1 Curvature term cancels 60% of BS drive for MAST case saturation  dw dt w seed Glasser-Greene-Johnson term a GGJ  D R  Equation from O. Sauter Phys. Plasmas 4, May 1997

35 Evolution can be well fit using modified Rutherford eqn. TM size responds to  p step down, and fit  is < 0  NTM Island width too large w/o GGJ term (  would be too negative) ion polarisationfinite island transportFit to decay requires either ion polarisation or finite island transport model (noise level) Island size (cm) /  p x 15 models 3730 data pp NBI (800kW) sawtooth/ELM transients q-profile measurements needed for   NSTX this year M.R. Eqn. derived for low-A & high-  (C. Hegna – PoP 1999) will also be used

36 Sawtooth seeding of TM strong in ST, not fully understood Sawtooth increases existing n=2 NTM width n=1 amplitude n=2 amplitude Sawtooth can excite n=2 on NSTX also… but, n=2 width can also decrease post-crash (R.J. Buttery) (E. Fredrickson) On MAST, sawtooth readily excites 3/2 NTM close to NTM marginal  Large q=1 surface radius and stronger magnetic coupling likely important n=1

37 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection and electron beam injection –Plasma merging/compression and PF-coil direct induction

38 J.E. Menard – MHD SFG – 5/19/ The ST inherently accesses unique region of parameter space for fast-ion-driven MHD Typical operational scenarios have: –Low B, high n e lower V A –High  fast and high v fast /V A  Strong drive for Alfvénic modes  Excellent tests for theory/simulation Broad spectrum of modes often unstable simultaneously: –CAE: 1-3MHz (Compressional) –GAE: 0.3-1MHz (Global) –TAE: kHz (Toroidal) –Fishbone: 5-100kHz DIII-D

39 J.E. Menard – MHD SFG – 5/19/ ST & standard tokamak can test A-dependence of fast-ion MHD by operating in similar (low B T ) parameter regime At B(0)  T, NSTX & DIII-D observe: –EPM, TAE and CAE –Fast ion losses from EPM and TAE –Modes unstable when fast-ion β is high Differences: –NSTX TAE has lower n (from  R scaling) –Rapidly chirping/bursting (100kHz  10kHz) EPM much more common on NSTX Also observed on START/MAST  ST feature? NSTX DIII-D (Fredrickson - PPPL Heidbrink - UCI)

40 J.E. Menard – MHD SFG – 5/19/ Non-linear TAE simulations reproduce many features observed in NSTX data M3D Nonlinear Hybrid simulations: –Mode growth and decay times are approximately  s –Bursting/chirping behavior results from: Non-linear modification of fast-ion distribution Change in mode structure Data Simulation t=0.0t=336 (G. Fu - PPPL) n=2 Simulations  Mode moves radially outward during amplitude saturation phase

41 J.E. Menard – MHD SFG – 5/19/ GAE/CAE unstable at higher k || and high v fast / v A > 2 HYM simulations of GAE and CAE –Nonlinear, global, fully kinetic ions –Beam ions treated with full-orbit  f method GAE found to be most unstable (  <  ci ) –  =  ci just below the lower edge of the Alfven continuum  < MIN(  A ) –2  n  7, several m unstable for each n –Localized near magnetic axis –  B ||   B  / 3 Higher-n modes more compressional (CAE) –  B || >  B  –  =  ci –7  n  10, weakly unstable compared to GAE –Localized near outboard midplane Beam ion resonance condition: (Electron Landau and thermal ion cyclotron damping weak) VZVZ VRVR (E. Belova - PPPL)

42 J.E. Menard – MHD SFG – 5/19/ Impact of fast-ion MHD on confinement can be significant Bursting/chirping EPMs correlate w/ large fast ion loss CAE bursts coincident w/ EPM onset suggest CAE-induced fast ion transport Are CAE modes large enough to stochastically heat thermal ions? (Gates, White - PPPL) Phys. Rev. Lett. 87, (2001) (Fredrickson - PPPL) Need internal measurement of CAE  B to assess role in fast-ion transport & stochastic heating

43 J.E. Menard – MHD SFG – 5/19/ ST configuration impacts full spectrum of MHD activity Internal kink mode –Flow-shearing rate ~  linear w/o rotation –Rotation + enhanced  *  possible saturation mechanism? Resistive Wall Mode (RWM) –Low A, high edge-q, and large v Sound / v Alfvén impact critical   –Higher plasma  (lower S) may impact RWM  scaling Edge Localized Modes (ELM) –Strong intrinsic shaping enhances pedestal stability –Larger rotational shear may also enhance stability Neoclassical Tearing Modes (NTM) –Low-A enhances toroidal curvature effects –Toroidal mode coupling stronger, q=1 radius larger Alfvén Eigenmodes (*AE) and Energetic Particle Modes (EPM) –Intrinsically large v fast / v A and  fast  enhanced instability drive –Resonances at 1 st  ci harmonic Solenoid-free ST plasma formation –Coaxial helicity injection (CHI) and electron beam injection –Merging/compression (MC) and PF-coil direct induction

44 J.E. Menard – MHD SFG – 5/19/ Transient Coaxial Helicity Injection (CHI) Method attempts to force axisymmetric reconnection at injector to create equilibrium with closed flux surfaces (R. Raman – U. Washington) (Camera images – C. Bush)

45 J.E. Menard – MHD SFG – 5/19/ Experiment (NSTX, Raman, et al) Fast camera view 3D Simulation (CHIP code, NESRC 256 CPUs)  -averaged poloidal flux; n=1 helical kink CHI is helical instability cascading to relaxation Tang and Boozer, PoP, May 2004 Significant OH flux savings has been achieved on HIT-II using transient CHI Understanding from CHIP code (X. Tang - LANL) Line-tied kink driven unstable on open field lines Kink drives dynamo V LOOP in closed-flux region Closed-flux modes driven unstable by J-gradient  relaxation and current penetration

46 J.E. Menard – MHD SFG – 5/19/ Use MST-style gun current sources to inject helical current in divertor region Current amplification up to ~ 20 Merging / reconnection (?) above threshold power Closed flux surfaces requires field, gun optimization Noninductive ST Plasma Formation: Current Injectors in Divertor (R. Fonck – U. Wisconsin) 30ms

47 J.E. Menard – MHD SFG – 5/19/ Merging/Compression: plasma rings formed on or near ‘induction’ coils, then merged together Recent scheme proposed by TS-3/4 team - ‘Double Null Merging’ (DNM) - produces plasma at X-point rather than coil surface to reduce impurities Coils ECH Small Tokamak Coils ST High-  ST (TS-5 Proposal - Y. Takase, Y. Ono – U. Tokyo) Magnetic reconnection heats ions creating high-  plasma M/C method w/o X-point already used on START and MAST in U.K. Small Tokamak

48 J.E. Menard – MHD SFG – 5/19/ MAST recently produced 1 st example of 300kA DNM plasma Plasma is dense (9  m -3 ) and hot (~0.5keV) (From A. Sykes – Culham, UK) A B C D EF MAST benefits from internal coils; NSTX will test with external coils

49 J.E. Menard – MHD SFG – 5/19/ kA tokamak formed using outboard PF coil induction HHFW antenna used as ionization source in outboard field null B Z ramp supplies loop voltage and vertical field B Z and B R evolution will be optimized to keep plasma in high V LOOP region  DINA modeling 8ms 9ms 10ms R  0  Low V LOOP (Camera images – C. Bush)

50 J.E. Menard – MHD SFG – 5/19/ The ST is a unique & important platform for testing MHD theory and simulation Low–A  high   + strong intrinsic shaping NBI drives near-Alfvénic rotation + *AE modes Unique ST features highlight MHD theory needs: 1/1 mode Non-linear evolution with flow, 2-fluid, hot particles RWM Self-consistent kinetic damping in general geometry +  ELM Rotation, , and  * effects + non-linear evolution NTM 2-fluid treatment for high- , general geometry + seeding *AE, EPM Self-consistent non-linear treatment of multiple *AE I P creation Dynamo, relaxation, reconnection  high I P w/ closed 

51 J.E. Menard – MHD SFG – 5/19/ I think we all agree that… From Horizon Casino

52 J.E. Menard – MHD SFG – 5/19/ Backup Material

53 Fitted parameters close to theoretical values  ’ adjusted to match saturated island size field curvature fixed to theory - bootstrap allowed to vary Good match to predicted drive - confirms BS/GGJ physics Field curvature stabilises 60% of bootstrap drive  r reduced - island affecting resistivity? 


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