1. Equilibrium and Stability of Oblate Free-Boundary FRCs in MRX S. P. Gerhardt, E. Belova, M. Inomoto*, M. Yamada, H. Ji, Y. Ren Princeton Plasma Physics Laboratory * Osaka University Talk and Movies Available at http://w3.pppl.gov/~sgerhard/seminar.htmlhttp://w3.pppl.gov/~sgerhard/seminar.html Linked from PPPL Employee Homepage

2. Outline Introduction –Brief overview of relevant FRC issues –Introduction to the MRX facility –FRC formation by spheromak merging Overview of FRC Stability Results in MRX Systematic Studies of FRC Stability –n=1 tilt/shift instabilities without passive stabilization –n  2 modes often limit lifetime after passive stabilizer is installed Modeling of Equilibrium and Stability Properties –Equilibrium reconstruction with new Grad-Shafranov code –Oblate Plasmas are Tilt Stable from a Rigid-Body Model –HYM calculations of Improved Stability Regime at Very Low Elongation Conclusions -E. Belova

3. FRCs have Potential Advantages as Fusion Reactors FRC  toroidal plasma configuration, with toroidal current, but minimal toroidal field.

4. FRCs have Potential Advantages as Fusion Reactors FRC  toroidal plasma configuration, with toroidal current, but minimal toroidal field. Intrinsically high  (  ~1) Natural divertor structure Only circular axisymmetric coils No material objects linking plasma column (ideally) Translatable (formation and fusion in different places) H. Guo, Phys. Rev. Lett. 92, 245001

5. FRCs have Potential Advantages as Fusion Reactors FRC  toroidal plasma configuration, with toroidal current, but minimal toroidal field. Problem: Often Predicted to Be Quite MHD Unstable H. Guo, Phys. Rev. Lett. 92, 245001 Pressure Contours, Disruptive Internal Tilt Belova et al, Phys. Plasmas 2000

6. FRC Stability is an Unresolved Issue Internal Tilt Mode in Prolate FRC (n=1) Plasma current ring tilts to align its magnetic moment with the external field. Growth rate is the Alfven transit time. Essentially always unstable in MHD. Never conclusively identified in experiments. FLR/non-linear saturation effects almost certainly important. (Belova, 2004) MHD Internal Tilt, Field Lines R.D. Milroy, et al, Phys. Fluids B 1, 1225 Pressure Contours, Disruptive Internal Tilt Belova et al, Phys. Plasmas 2000

7. FRC Stability is an Unresolved Issue Plasma current ring tilts to align its magnetic moment with the external field. Growth rate is the Alfven transit time. Essentially always unstable in MHD. Never conclusively identified in experiments FLR/non-linear saturation effects almost certainly important. (Belova, 2004) Oblate FRC: Internal Tilt  External Tilt (n=1) MHD External Tilt Mode, Pressure Contours Horiuchi & Sato, Phys. Fluids B 1, 581 For E<1, tilt becomes an external mode Can be stabilized by nearby conducting structures, or by very low elongation. Radial shifting mode may become destabilized. Observed in oblate FRC experiments, avoided with passive stabilizers. Internal Tilt Mode in Prolate FRC (n=1)

8. FRC Stability is an Unresolved Issue Plasma current ring tilts to align its magnetic moment with the external field. Growth rate is the Alfven transit time. Essentially always unstable in MHD. Never conclusively identified in experiments FLR/non-linear saturation effects almost certainly important. (Belova, 2004) Oblate FRC: Internal Tilt  External Tilt (n=1) Co-Interchange Modes n  2 cousins of tilt/shift modes For n , these are ballooning-like modes Low n co-interchange modes (1<n<9) computed to be destructive to oblate FRCs (Belova, 2001). Never experimentally studied. Pressure isosurface for n=2 axial co-interchange, calculated by HYM code Internal Tilt Mode in Prolate FRC (n=1) For E<1, tilt becomes an external mode Can be stabilized by nearby conducting structures, or by very low elongation. Radial shifting mode may become destabilized. Observed in oblate FRC experiments, avoided with passive stabilizers.

9. MRX is a Flexible Facility for Oblate FRC Studies Spheromak merging scheme for FRC formation. FRC shape control via flexible external field (EF) set. Describe EF by Mirror Ratio (MR) Extensive internal magnetic diagnostics. Passive stabilization via a conducting center column (sometimes). First experiments in spring 2005. 53904 52169 52191 51891 MR=2.0 MR=2.4 MR=3.0 MR=4.0

10. Comprehensive Diagnostics For Stability Studies 90 Channel Probe: 6x5 Array of Coil Triplets, 4cm Resolution, Scannable 105 Channel Toroidal Array: 7 Probes 5 coil triplets Toroidal Mode Number n=0,1,2,3 in B Z, B R, B T T i through Doppler Spectroscopy (He +1 @ 468.6nm) Copper Center Column for Passive Stabilization 10cm radius,.5 cm thick, axial cut

11. FRC Formation By Spheromak Merging 1: Plasma Breakdown 2: Spheromak Formation 3: Spheromak Merging 4: Final FRC Technique developed at TS-3, utilized on TS-4 and SSX Figure Courtesy of H. Ji.

12. Overview of MRX Results

13. Long-Lived FRC with Large Mirror Ratio & Passive Stabilizer Movie of Shot 52259

14. Passive Stabilizer and Shape Control Extend the Plasma Lifetime Poloidal Flux (Wb) B R n=1 (T) B R n=2 (T) Black Traces Merging End Time 53904, MR=2.1

15. Passive Stabilizer and Shape Control Extend the Plasma Lifetime Poloidal Flux (Wb) B R n=1 (T) B R n=2 (T) Black Traces Red Traces Merging End Time 53904, MR=2.1 52181, MR=2.5

16. Passive Stabilizer and Shape Control Extend the Plasma Lifetime Poloidal Flux (Wb) B R n=1 (T) B R n=2 (T) Black Traces Red Traces Blue Traces Large Non-Axisymmetries Before Merging Completion 53904, MR=2.1 52181, MR=2.5 52259, MR=3.4

17. Systematic Instability Studies Have Been Performed The instabilities have the characteristic of tilt/shift and co-interchange modes. The center column reduces the n=1 tilt/shift amplitude. Co-interchange (n  2) modes reduced by shaping more than by the center column. Co-interchange modes can be as deadly as tilting.

18. Axial Polarized Mode Appears Strongly in B R Z Z For n=1  Tilt mode Consider Tilting to Predict Magnetics Structure n=2 Axial Co-Interchange

19. Axial Polarized Mode Appears Strongly in B R B R, HYM Z Z n=2 Axial Co-Interchange 52182 B R, Data Pressure isosurfaces at p=0.7p o Calculated for MRX equilibria from HYM code

20. Radial Polarized Mode Appears Strongly in B Z Z Z B Z Perturbation at Midplane Pressure isosurfaces at p=0.7p o Calculated for MRX equilibria from HYM code n=3 Radial Co-interchange B Z, HYM B Z, Data

21. n=1 Tilt Observed Without Center Conductor No center conductor n=1 (tilt) dominates B R spectrum, especially for MR<2.5 1.8<MR<4.5  0.3<index<3 B R, n=1B R, n=2B R, n=3 No Center Conductor Helium

22. Center Column Reduces Tilt Signature B R, n=1B R, n=2B R, n=3 n=1 (tilt) reduced with center column n=2&3 axial modes reduced at large mirror ratio No Center Conductor Center Conductor Helium

23. n=1 Shifting Signature Observed Without Center Conductor B Z, n=1B Z, n=2B Z, n=3 Helium No center conductor n=1 (shift) increases with mirror ratio No Center Conductor Center Conductor

24. n=1 Shifting Signature Largely Suppressed with Center Column B Z, n=1B Z, n=2B Z, n=3 n=1 reduced by center column n=2 & 3 not changed by the passive stabilizer No Center Conductor Center Conductor Helium No Center Conductor Center Conductor

25. Lifetime is Strongly Correlated with B R Perturbations With Center- Column B R, n=1 B R, n=2 Large Mirror Ratio Small Mirror Ratio Helium

26. Lifetime is Strongly Correlated with B R Perturbations With & Without Center-Column Large Mirror Ratio Small Mirror Ratio B R, n=1 B R, n=2 Helium

27. Lifetime is Strongly Correlated with B R Perturbations B Z, n=1 B Z, n=2 With & Without Center-Column No Correlation with BZ Perturbation. Large Mirror Ratio Small Mirror Ratio B R, n=1 B R, n=2 Helium

28. Lifetime is Strongly Correlated with B R Perturbations With & Without Center-Column Helium Large Mirror Ratio Small Mirror Ratio B R, n=1 Helium B R, n=2 Helium With & Without Center-Column Neon B R, n=1 Neon B R, n=2 Neon Helium & Neon

29. Multiple Tools Used to Model Oblate FRCs MHD equilibria computed using new free- boundary Grad-Shafranov solver. Simple rigid-body model used to estimate rigid body shifting/tilting. MHD computations with the HYM code. Calculation by E. Belova

30. Multiple Tools Used to Model Oblate FRCs MHD equilibria computed using new free- boundary Grad-Shafranov solver. Plasmas shape modifications due to external field are important to understand. Stability modeling requires knowledge of current profile, pressure profile, external field,… 90-channel probe scan lacks coverage area and axisymmetry. N-Probes lack information Z  0. Equilibrium reconstruction can solve these problems. First ever application of this technique to an FRC plasma. Large non-axisymmetries present…calculate “nearby” equilibrium.

31. Modify forms of p’(  ) and FF’(  ), and use  calculate from magnetics data. Using p(  ) and F(  ), calculate new J  =2  Rp’+2  0 FF’/R Use new J  & Coil Currents to calculate new  Store  as  old Compare  to  old Converged Didn’t Converge Reevaluate P and F with new  G-S Solver Loop Find separatix flux (  sep ) using contour following algorithm If not Iteration 1: Compare  2 to  2 old. Store  2 as  2 old. Didn’t Converge Predict diagnostic signals based on equilibria. Compute  2 Plotting and post- processing. Create input based on MRX data: 1: 90 Channel Probe Scan 2: n=0 Component of N- Probes 3: Coil Currents Create guesses to the  distribution 2 and p’(  ) and FF’(  ). MRXFIT 1 Solves G-S Eqn. Subject to Magnetic Constraints 1) J.K. Anderson et.al. Nuclear Fusion 44, 162 (2004) 2) S.B. Zheng, A.J. Wooten, & E. R. Solano, Phys. Plasmas 3,1176 (1996) Converged

32. Fields Calculated From Axisymmetric Model With Flux Conserving Vessel *J.K. Anderson et.al. Nuclear Fusion 44, 162 (2004) Equilibrium Field Coils Vacuum Vessel is Treated as a Flux Conserver Shaping Field Coils 2 Turns Per Coil Flux Core PF Windings 4 Turns Per Coil Windings of Future Ohmic Solenoid

33. Fields Calculated From Axisymmetric Model With Flux Conserving Vessel *J.K. Anderson et.al. Nuclear Fusion 44, 162 (2004) Equilibrium Field Coils Vacuum Vessel is Treated as a Flux Conserver Shaping Field Coils 2 Turns Per Coil Flux Core PF Windings 4 Turns Per Coil Windings of Future Ohmic Solenoid Coils Only Coils & Flux Conserver Measurement

34. MRXFIT Code Finds MHD Equilibria Consistent with Magnetics Data Iterative free-boundary Grad- Shafranov solver. Flexible Plasma Boundary Center Column Limited SF Coil Limited X-points P’(  ) & FF’(  ) optimized for solution matching measured magnetics. Equilibria interfaced to HYM stability code.

35. Equilibrium Properties Respond to the External Field (-Z T,R T ) (Z T,R T ) (0,R i ) (0,R o ) Center Conductor *S.B. Zheng, A.J. Wooten, & E. R. Solano, Phys. Plasmas 3,1176 (1996) Definitions*: Center Conductor No Center Conductor Pink region: Caution! Large Non-axisymmetries!

36. Rigid-Body Model Used to Estimate Tilt/Shift Stability H. Ji, et al, Phys. Plasmas 5, 3685 (1998) Torque Tilting Shifting Force Tilting Stable: n>1 Radial Shifting Stable: n<0

37. MRX Plasmas Transition to the Tilt Stable Regime Plasmas with MR>2.5 predicted to be in the tilt-stable regime. Simple model for center-column m=1 eddy currents used. Marginal comparison: Tilt often develops during merging phase.

38. Rigid Body Shift Often Present, But May Be Benign 270  s 280  s290  s350  s 340  s 330  s320  s310  s300  s

39. Rigid Body Shift Often Present, But May Be Benign Midplane B Z contours at time of large shift 270  s 280  s290  s350  s 340  s 330  s320  s310  s300  s

40. Rigid Body Shift Often Present, But May Be Benign Hypothesis: Strong field at large radius prevents destructive shift

41. HYM Calculations Indicate Reduced Growth Rates at Larger Mirror Ratio 4 Configurations Considered So Far Increasing mirror ratio Calculations By E. Belova

42. HYM Calculations Indicate Reduced Growth Rates at Larger Mirror Ratio Increasing mirror ratio Consider MR=2.5 case N  /  o, Measured  /  o, HYM 2, axial10.3 3, axial1.40.7 N  /  o, Measured  /  o, HYM 2, radial1.20.65 3, radial20.8 Consider MR=3.0 case

43. Local Mode Stability Improves At High Mirror Ratio Ishida, Shibata, & Steinhauer Rigid Displacement, n>>1 limit J.R. Cary, Phys. Fluids 24, 2239 (1981) A. Ishida et al, Phys. Plasmas 3, 4278 (1996) HYM Ishida Estimate Growth Rates for Local Modes Reduced at Higher Mirror Ratio. Ishida Estimate Radially Polarized n=4 Axially Polarized n=4

44. Results Supportive of Proposed SPIRIT* Program Merging spheromaks for formation of oblate FRC. Process has been demonstrated in MRX. Shaping and passive conductors to stabilize n=1 modes. Demonstrated to work with a center column. –SPIRIT program calls for conducting shells. Transformer to increase B and heat the plasma. –Prototype transformers under construction using laboratory funds. Neutral beam to stabilize dangerous n  2 modes. –Need for beam is clearly demonstrated, especially at lower elongation. (*Self-organized Plasma with Induction, Reconnection, and Injection Techniques)

45. Conclusions FRCs formed in MRX under a variety of conditions Large n=1 tilt/shift instabilities observed in MRX plasmas without passive stabilization. Shaping + passive stabilization substantially reduces n=1 modes, but destructive n  2 axial modes often remain. A regime with small elongation demonstrates improved stability to n  2 axial modes and extended lifetime. Equilibrium reconstruction technique has been demonstrated, illustrating FRC boundary control. The improved stability in the small elongation regime is confirmed by a combination of modeling techniques.

46. Derivation of Formula For Local Mode Growth Rate P1 P2 P1: I. B. Bernstein, E.A. Frieman, M.D. Kruskal, and R.M. Kulsrud, Proc. Royal Society A 244, 17 (1958) P2: J.R. Cary, Phys. Fluids 24, 2239 (1981) P3: A. Ishida, N. Shibata, and L.C. Steinhauer, Phys. Plasmas 3, 4278 (1996) P4: A. Ishida, N. Shibata, and L.C. Steinhauer, Phys. Plasmas 1, 4022 (1994) P2 & P3 P2 First Written Explicitly in Ishida, Shibata, and Steinhauer, Phys. Plasmas 3, 4278 (1996) Approximate agreement with Variational Analysis for Prolate FRCs in P4

47. Plasma Parameters D2D2 HeliumNeon Fill Pressure (mTorr, molecules/cm -3 ) 8-10, 3x10 14 7-9.5, 2x10 14 3.5-5, 1.3x10 14 n e, T e 1x10 14, 10(1-2)x10 14,10-14(2-3)x10 14, 10 B Z,Sep (Gauss).03-.02 V A (m/s)3-2x10 4 2-3x10 4 1x10 4 Z S (m)  A (  s) 3-75-1010-30 i,mfp (cm) 432  ci  i 110.5 3-11.5-1 E.6-.3 7-42-3

48. Plasma Lifetime Longest At Large Mirror Ratio 2 Trends Lifetime increases with larger mirror ratio. Center column does not substantially increase the lifetime. Helium Neon

49. Condition For Kinetic Effects Kinetic effects matter when: The Diamagnetic drift Frequency is: Note that for  ~1: The wavenumber is related to the Major radius as: The separatrix radius is related to the null radius by: Combine these as:

50. Neon Tilting Suppressed With Center Column B R, n=1 B R, n=2 B R, n=3 Neon No Center Conductor Center Conductor

51. Center Column Reduces Rigid Body Shift Signature B Z, n=1 B Z, n=2B Z, n=3 Neon No Center Conductor Center Conductor

52. Analytic Equilibrium Model by Zheng Provides Approximation to Current Profile (-Z T,R T )(Z T,R T ) (0,R i ) (0,R o ) 6 Fit parameters in Model: 4 Parameters determine the Plasma shape 2 Parameters determine Pressure and Toroidal field: Poloidal flux specified as: Magnetic Field: Used to Generate Initial Equilibrium for MRXFIT S.B. Zheng, A.J. Wooten, & E. R. Solano, Phys. Plasmas 3,1176 (1996)

53. Spheromak Tilt is Dominated by n=1 B R, n=1 B R, n=2 B R, n=3

54. Strong n=1 during Tilting Spheromak

55. Poor FRC with no Passive Stabilizer and Low Mirror Ratio Movie of Shot 54154

56. Lifetime Not Longer with the Stabilizer at Low Mirror Ratio Movie of Shot 52181