Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST

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Ion Heating During Local Helicity Injection Plasma Startup in the Pegasus ST M.G. Burke, J.L. Barr, M.W. Bongard, R.J. Fonck, E.T. Hinson, J.M. Perry, J.A. Reusch 57 th Annual Meeting of the APS-DPP University of Wisconsin-Madison Savannah, GA November 17, 2015 PEGASUS Toroidal Experiment

Outboard LHI Provides Robust Startup on the PEGASUS ST I p 0.18 MA via LHI (I inj = 5 ka) Injected Current Stream Local Helicity Injectors I BIAS B TF = 0.1 T I ARC Plasma Parameters I p 0.23 MA τ shot 0.025 s B T 0.15 T A 1.15 1.3 R 0.2 0.45 m a 0.4 m κ 1.4 3.7 Injector Parameters I inj 14 ka I inj 2 ka V inj 2.5 kv N inj 4 A inj = 2 cm 2 I arc 2 ka 0.5 kv V arc Vessel GND

Ion Spectroscopy Diagnostic Deployed to Study Local Helicity Injection on Pegasus Diagnostic Characteristics: Spectrometer: UV 1m f/8.6 Czerny-Turner, 1200 g/mm blazed @ 1 um Spectral Range: 200 800 nm Spectral Resolution: 0.13 Å Total etendue: 8 10-4 cm 2 -str @ 0.1 mm slit Detector: UV Intensified Fast CMOS (Phantom v310) Flexible frame rate: 1-500 khz M. G. Burke, et al., Rev. Sci. Instrum. 83, 10D516 (2012) Max Time resolution: 1 MHz

LHI Plasmas Studied Using Multiple Viewing Chords 19x 1mm Quartz fibers used for collection Tangential viewing chords cover R = 25 to 80 cm with 4 cm resolution Poloidal views at R = 80 and 65 cm Single radial chord All chords recorded simultaneously with the possibility of adding additional fibers to increase SNR Top Down Cutaway

Magnetic Reconnection Activity Observed in NIMROD Simulation and Experiment During LHI Current rings in NIMROD* Observed current rings in PEGASUS (pre-tokamak plasma) Multiple merging events Multiple merging events Injected current ring Single merging event: Adjacent passes merge Current ring formation * J. O Bryan, et al., Physics of Plasmas, 19, 080701 (2012) Adjacent injector stream passes J. O Bryan, C.R. Sovinec, Plasma Phys. Control. Fusion 56 064005 (2014)

NIMROD Simulations of LHI on Pegasus Show Magnetic Reconnection Activity and Bursty MHD MHD bursts accompany I p growth Localized in edge* n=1 line-tied kink structure NIMROD Coherent streams persist in edge, matching NIMROD predictions [O Bryan Phys Plas.19, 2012] NIMROD and experiment see wave excited at Alfven frequencies for device scale wavelengths Suggests edge localized reconnection Internal Hall Probe Measurements PEGASUS * E.T. Hinson, Ph.D. Thesis, UW-Madison, 2015.

Magnetic Reconnection Leads to Ion Heating in a Variety of Plasmas Anomalous ion heating observed during magnetic reconnection in numerous devices such as MRX, TS-3, MST, HIT-II, MAST, SSX, etc., and in astrophysical plasmas MRX TS-3, MAST MST J. Yoo, M. Yamada, H. Ji, and C. E. Myers, Phys. Rev. Lett., vol. 110, no. 21, p. 215007, 2013. HIT-II, Helicity Injection I p Y. Ono et al., Plasma Phys. Control. Fusion, vol. 54, no. 12, p. 124039, 2012. G. Fiksel, et al., Phys. Rev. Lett., vol. 103, no. 14, p. 145002, Sep. 2009. R. G. O'Neill et al., Phys. Plasmas, vol. 12, no. 12, p. 122506, 2005.

LHI Current Drive in PEGASUS Leads to Continuous Impurity Ion Heating Large impurity temperatures temporally correlated with large magnetic oscillations near the plasma edge T i >T e during LHI current drive phase Immediately following handoff to Ohmic current drive, T i < 1/4T e Large T i attributed to ion heating due to magnetic reconnection LHI T e,peak,lhi ~ 140 ev Ohmic T e,peak,oh > 140 ev

Impurity Spectral Profiles During LHI Reveal Edge Localized Heating and Apparent Non-thermal Distributions Studies of different impurity lines present in LHI plasmas performed in order to understand ion heating characteristics and dynamics 70cm 55cm 36cm Radial Impurity scan time point Helicity injectors Impurity scan spatial points

Oxygen-V Spectral Profiles Indicate Edge Ion Heating, Diffusion of Energy to Plasma Core Radial 36cm 55cm 70cm Edge OV temperature much larger than core temperature during LHI In a comparable Ohmic plasma with similar applied loop voltage T i,ov ~ 50 ev Initial Thomson profiles indicate T e ~140 ev, peaked in plasma core (See David Schlossberg APS Poster) OV, OVI terminal charge state

OV Emissivity Profile Peaked in Core, T i,core Uncontaminated by Hot Edge Emission Onion peeling method used to calculate emissivity, Abel integral used to forward model T i, (R) 1 gg rr rr Abel Integral: II yy = 2 yy rr 2 yy dddd 2 Onion: gg = DD 1 II Forward modeling of a prescribed temperature profile shows that the hot edge component does not pollute core temperature T i,core = 50 ev T i,core = 200 ev

Helium-II Impurity Spectral Distributions Appear Nonthermal during LHI Radial 36cm 55cm 70cm Plasma edge chord shows clear bi-gaussian (nonthermal) spectral profile High signal-to-noise needed to resolve bi-gaussian Profiles fit using analytic form of multi-gaussian convolution with 3-gaussian instrument profile

Heidi and OV Thermalization Times help Explain Differences in Observed Spectral Profiles υυ EE HHHHHHHH,HHHHHHHH υυ EE OOOO,OOOO = 1 128 TT ii,oooo + TT ii,oooo,hoooo 3/2 TT ii,hhhhhhhh + TT ii,hhhhhhhh,hoooo 3/2 Δxx rrrrrrrrrrrr Δtt 1 5 cccc/ss υυ EE OOOO,OOOO 526 ss 1 xx OOOO,ttttttttt 5.4 cccc xx HHHHHHHH,ttttttttt 750 cccc Thermalization length ~100 times larger for HeII than for OV explaining the persistence of the double Gaussian HeII spectral profile across the plasma major radius

High Speed HeII T i Measurements Indicate Edge Localized Heating and Temporal Correlation with Bursty MHD BB [T/s] Using single temperature fits, HeII heating temporally correlates with bursty MHD linked to reconnection activity (NIMROD)

Ion Heating is Toroidally Symmetric and Not due to Sightline Intersection with Local Injector Emission 55cm Injector 4 Only 70cm Single injector driven discharges: Injector 1 Only

Upon Fast Interruption of I inj, Apparent Non-thermal He-II Spectral Profiles Quickly Become Thermal Radial 55cm 36cm 70cm

Reconnection Theory Allows for Testing of Scaling on PEGASUS Two-fluid effects inside the ion diffusion region lead to the development of an inplane electrostatic potential Consideration of electron momentum equations allows the estimation of the inplane electric field: ddvv ee nn ee mm ee dddd = eenn ee EE + vv ee BB pp + eenn ee ηη JJ EE RR VV eeee BB ZZ 1 eenn ee pp ee dddd φφ = ddddee RR dddd 1 eenn ee J. Yoo, M. Yamada, H. Ji, and C. E. Myers, Phys. Rev. Lett., vol. 110, no. 21, p. 215007, 2013. JJ YY BB ZZ pp ee RR BB 2 rrrrrr φφ 2μμ 0 ee nn ee + TT ee TS-3 and MAST merging tokamak experiments found temperature increment scaled with TT ii ~vv 2 AA ~BB 2 rrrrrr /nn Detailed studies at MRX show ions being accelerated by in-plane electric field Y. Ono et al., Plasma Phys. Control. Fusion, vol. 54, no. 12, p. 124039, 2012.

Experiment Preformed to Isolate Heating due to Reconnection Between Adjacent Current Streams No current in stream Current in stream Impurity gas injection Injectors Center stack Stream density set by double layer density at injector which in turn is set by injector parameters * II DDDD ~ββnn ssssssssssss VV DDDD, I DL and V DL are injector parameters I inj and V inj From reconnection theory, ion kinetic energy gain expressed in terms of measurable parameters: φφ BB 2 rrrrrr + TT 2μμ 0 ee nn ee φφ ee * E.T. Hinson, Ph.D. Thesis, UW-Madison, 2015. II iiiiii / 2 II iiiiii VV iiiiii KKKK iiiiii qq mm II bbbbbbbb VV bbbbbbbb

Heating Observed in Biased Current Streams Scales with Parameters Predicted by Two-fluid Reconnection Theory Sightline perpendicular to current streams indicates large amounts of heating on the HeII spectral line TT ii, TT ii, Sightline parallel to the streams see little to no heating, consistent with radial flows out of a X- point Spectral profiles fit well with single temperature distribution Sample spectral profile from scan:

TT ii,hhhhhhhh Changes with both II iiiiii and VV iiiiii and Scales Linearly with Toroidal Field Strength (Guide Field) Heating changes with both II iiiiii and VV iiiiii : Heating increases linearly with BB tttttt : T i,heii [ev] II iiiiii VV iiiiii [a.u.]

I iiiiii VV iiiiii Scanned While Looking at CIII T i TT ii, TT ii, II iiiiii VV iiiiii [a.u.] CIII TT ii, >> TT ii,, similar to HeII CIII TT ii, appears to saturate at high values of II iiiiii VV iiiiii

Potential q/m Scaling of Heating Explored By Comparing C-II and C-III T i +4mmmm Peak at 400 (CII) either moved or confused by broadening of Peak 0 Kinetic energy of ions being accelerated by in-plane electric field should scale ~ qq iiiiii mm iiiiii CII T i initially appears much lower than CIII however spectrum is complex

Summary Continuous edge ion heating observed during steady helicity injection current drive Ion heating penetrates to plasma core as indicated by high core T i,ov and forward modeling on spatial emissivity profiles Impurity T i > T e during LHI driven discharges and is temporally correlated with large MHD activity Additionally, T i,lhi >> T i,ohmic HeII T i found to scale with parameters predicted by magnetic reconnection theory