T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting1 T. M. Biewer, R.E. Bell October 20 th, 2003 NSTX Physics Meeting Princeton Plasma Physics Laboratory.

Slides:



Advertisements
Similar presentations
Ion Heating and Velocity Fluctuation Measurements in MST Sanjay Gangadhara, Darren Craig, David Ennis, Gennady Fiskel and the MST team University of Wisconsin-Madison.
Advertisements

Biased Electrodes for SOL Control in NSTX S.J. Zweben, R.J. Maqueda*, L. Roquemore, C.E. Bush**, R. Kaita, R.J. Marsala, Y. Raitses, R.H. Cohen***, D.D.
Institute of Interfacial Process Engineering and Plasma Technology Gas-puff imaging of blob filaments at ASDEX Upgrade TTF Workshop.
High speed images of edge plasmas in NSTX IEA Workshop Edge Transport in Fusion Plasmas September 11-13, 2006 Kraków, Poland GPI outer midplane – shot.
STATUS OF THE HHFW CURRENT DRIVE EXPERIMENT ON NSTX Phil Ryan, Randy Wilson, David Swain, Bob Pinsker March 3, 2004 run date. This XP is focused on CD.
Plasma Dynamics Lab HIBP Abstract Measurements of the radial equilibrium potential profiles have been successfully obtained with a Heavy Ion Beam Probe.
Physics of fusion power
13th IEA/RFP Workshop – Stockholm October 9-11, D characterization of thermal core topology changes in controlled RFX-mod QSH states A. Alfier on.
HEAT TRANSPORT andCONFINEMENTin EXTRAP T2R L. Frassinetti, P.R. Brunsell, M. Cecconello, S. Menmuir and J.R. Drake.
FIDA Diagnostic Diagnostic for FAST IONS : it measures the vertical component of perpendicular energy Processes generating fast ions –Beam –ICRH heating.
49th Annual Meeting of the Division of Plasma Physics, November , 2007, Orlando, Florida Ion Temperature Measurements and Impurity Radiation in.
D. Borba 1 21 st IAEA Fusion Energy Conference, Chengdu China 21 st October 2006 Excitation of Alfvén eigenmodes with sub-Alfvénic neutral beam ions in.
A. HerrmannITPA - Toronto /19 Filaments in the SOL and their impact to the first wall EURATOM - IPP Association, Garching, Germany A. Herrmann,
9/20/04NSTX RESULTS REVIEW NSTX rtEFIT implementation progress results NSTX 2004 RESULTS REVIEW September 20&21, 2004 REAL-TIME EQUILIBRIUM RECONSTRUCTION.
10th ITPA TP Meeting - 24 April A. Scarabosio 1 Spontaneous stationary toroidal rotation in the TCV tokamak A. Scarabosio, A. Bortolon, B. P. Duval,
Edge Neutral Density (ENDD) Diagnostic Overview Patrick Ross Monday Physics Meeting Monday, March19, 2007.
XP NSTX Results Review Beam Modulation Effects on Ion Power Balance XP 737 P.W.Ross.
Initial Exploration of HHFW Current Drive on NSTX J. Hosea, M. Bell, S. Bernabei, S. Kaye, B. LeBlanc, J. Menard, M. Ono C.K. Phillips, A. Rosenberg, J.R.
Plasma Dynamics Lab HIBP E ~ 0 V/m in Locked Discharges Average potential ~ 580 V  ~ V less than in standard rotating plasmas Drop in potential.
J.R. Wilson, R.E. Bell, S. Bernabei, T. Biewer, J. C. Hosea, B. LeBlanc, M. Ono, C. K. Phillips Princeton Plasma Physics Laboratory P. Ryan, D.W Swain.
12/03/2013, Praga 1 Plasma MHD Activity Observations via Magnetics Diagnostics: Magnetic island Analysis Magnetic island Analysis Frederik Ostyn (UGent)
V. A. Soukhanovskii 1 Acknowledgement s: R. Maingi 2, D. A. Gates 3, J. Menard 3, R. Raman 4, R. E. Bell 3, C. E. Bush 2, R. Kaita 3, H. W. Kugel 3, B.
Flow and Shear behavior in the Edge and Scrape- off Layer in NSTX L-Mode Plasmas Y. Sechrest and T. Munsat University of Colorado at Boulder S. J. Zweben.
1 Results and analysis of Gas Puff Imaging experiments in NSTX: turbulence, L-H transitions, ELMs and other phenomena R.J. Maqueda Nova Photonics S.J.
Tunable, resonant heterodyne interferometer for neutral hydrogen measurements in tokamak plasmas * J.J. Moschella, R.C. Hazelton, M.D. Keitz, and C.C.
OPERATIONAL SCENARIO of KTM Dokuka V.N., Khayrutdinov R.R. TRINITI, Russia O u t l i n e Goal of the work The DINA code capabilities Formulation of the.
4 th ITPA Meeting Apr 03 LRB Rotation of Impurity Species in the DIII-D Tokamak and Comparison with Neoclassical Theory L.R. Baylor, K.H. Burrell*, R.J.
Physics of fusion power Lecture 9 : The tokamak continued.
14 Oct. 2009, S. Masuzaki 1/18 Edge Heat Transport in the Helical Divertor Configuration in LHD S. Masuzaki, M. Kobayashi, T. Murase, T. Morisaki, N. Ohyabu,
2 The Neutral Particle Analyzer (NPA) on NSTX Scans Horizontally Over a Wide Range of Tangency Angles Covers Thermal ( keV) and Energetic Ion.
NSTX Boundary Density Fluctuation Measurement by FIReTIP System with USN/LSN Configurations K.C. Lee, C.W. Domier, M. Johnson, N.C. Luhmann, Jr. University.
Supported by 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.
Advances In High Harmonic Fast Wave Heating of NSTX H-mode Plasmas P. M. Ryan, J-W Ahn, G. Chen, D. L. Green, E. F. Jaeger, R. Maingi, J. B. Wilgen - Oak.
Study of NSTX Electron Density and Magnetic Field Fluctuation using the FIReTIP System K.C. Lee, C.W. Domier, M. Johnson, N.C. Luhmann, Jr. University.
NSTX EXPERIMENTAL PROPOSAL - OP-XP-825 Title: HHFW Heating/CD phase scans in D L-mode plasmas P. Ryan, J. Hosea, R. Bell, L. Delgado-Aparicio, S. Kubota,
Measurement of toroidal rotation velocity profiles in KSTAR S. G. Lee, Y. J. Shi, J. W. Yoo, J. Seol, J. G. Bak, Y. U. Nam, Y. S. Kim, M. Bitter, K. Hill.
Edge-SOL Plasma Transport Simulation for the KSTAR
Probe measurements on the GOLEM tokamak Vojtech Svoboda 1, Miglena Dimitrova 2, Jan Stockel 1,2 1 Faculty of Nuclear Physics and Physical Engineering,
HT-7 ASIPP The Influence of Neutral Particles on Edge Turbulence and Confinement in the HT-7 Tokamak Mei Song, B. N. Wan, G. S. Xu, B. L. Ling, C. F. Li.
Relationship Between Edge Zonal Flows and L-H Transitions in NSTX S. J. Zweben 1, T. Munsat 2, Y. Sechrest 2, D. Battaglia 3, S.M. Kaye 1, S. Kubota 4.
Objectives Much better spatial resolution Velocity space discrimination W. Heidbrink, M. Van Zeeland, J. Yu FIDA Imaging Proposal.
A. Vaivads, M. André, S. Buchert, N. Cornilleau-Wehrlin, A. Eriksson, A. Fazakerley, Y. Khotyaintsev, B. Lavraud, C. Mouikis, T. Phan, B. N. Rogers, J.-E.
Radial Electric Field Formation by Charge Exchange Reaction at Boundary of Fusion Device* K.C. Lee U.C. Davis *submitted to Physics of Plasmas.
Rajesh Maingi Oak Ridge National Laboratory M. Bell b, T. Biewer b, C.S. Chang g, R. Maqueda c, R. Bell b, C. Bush a, D. Gates b, S. Kaye b, H. Kugel b,
High Speed Imaging of Edge Turbulence in NSTX S.J. Zweben, R. Maqueda 1, D.P. Stotler, A. Keesee 2, J. Boedo 3, C. Bush 4, S. Kaye, B. LeBlanc, J. Lowrance.
T. Biewer, November 19 th, th APS-DPP 2004, Savannah, Georgia 1 of 18 Edge Ion Heating by Launched High Harmonic Fast Waves in NSTX Supported by.
1 Recent Studies of NSTX Edge Plasmas: XGC0 Modeling, MARFE Analysis and Separatrix Location F. Kelly a, R. Maqueda b, R. Maingi c, J. Menard a, B. LeBlanc.
Comparison between X-ray measurements with the GEM detector and EFIT calculations Danilo Pacella Present address: JHU, Baltimore, MD Permanent address:
HT-7 ASIPP The measurement of the light impurity radiation profiles for the impurity particle transport in the HT-7 tokamak Qian Zhou, B.N.Wan, Z.W.Wu,
Changes in Edge Turbulence with  * and Toroidal Rotation Input in NSTX M. Gilmore, S. Kubota, W.A. Peebles, and X.V. Nguyen Electrical Engineering Dept.,
Edge Turbulence in High Density Ohmic Plasmas on NSTX K.M. Williams, S.J. Zweben, J. Boedo, R. Maingi, C.E. Bush NSTX XP Presentation Draft 5/25/06.
Charge Exchange Spectroscopic Diagnostic for the TJ-II José Miguel Carmona Torres Laboratorio Nacional de Fusion EURATOM-CIEMAT.
1Field-Aligned SOL Losses of HHFW Power and RF Rectification in the Divertor of NSTX, R. Perkins, 11/05/2015 R. J. Perkins 1, J. C. Hosea 1, M. A. Jaworski.
Supported by 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.
Characterization of Fast Ion Power Absorption of HHFW in NSTX A. Rosenberg, J. Menard, J.R. Wilson, S. Medley, R. Dumont, B.P. LeBlanc, C.K. Phillips,
1 NSTX EXPERIMENTAL PROPOSAL - OP-XP-712 Title: HHFW Power Balance Optimization at High B Field J. Hosea, R. Bell, S. Bernabei, L. Delgado-Aparicio, S.
T. Biewer, March 3 rd, 2003NSTX Physics Meeting Measurements of Edge Impurity Ion Dynamics During RF Heating T. M. Biewer, R.E. Bell March 3 rd, 2003 NSTX.
Scaling experiments of perturbative impurity transport in NSTX D. Stutman, M. Finkenthal Johns Hopkins University J. Menard, E. Synakowski, B. Leblanc,R.
53rd Annual Meeting of the Division of Plasma Physics, November , 2011, Salt Lake City, Utah When the total flow will move approximately along the.
Initial Results from the Scintillator Fast Lost Ion Probe D. Darrow NSTX Physics Meeting February 28, 2005.
T. Biewer, Sep. 21 st, 2004 NSTX Results Review of 11 Dependence of Edge Flow on Magnetic Configuration in NSTX T.M. Biewer, R.E. Bell, D. Gates,
NSTX S. A. Sabbagh XP407: Passive Stabilization Physics of the RWM in High  N ST Plasmas – 4/13/04  Goals  Define RWM stability boundary in (V , 
NSTX APS-DPP: SD/SMKNov Abstract The transport properties of NSTX plasmas obtained during the 2008 experimental campaign have been studied and.
56 th Annual Meeting of the Division of Plasma Physics. October 27-31, New Orleans, LA Using the single reservoir model [3], shown on right, to:
Profiles of density fluctuations in frequency range of (20-110)kHz Core density fluctuations Parallel flow measured by CHERS Core Density Fluctuations.
NIMROD Simulations of a DIII-D Plasma Disruption S. Kruger, D. Schnack (SAIC) April 27, 2004 Sherwood Fusion Theory Meeting, Missoula, MT.
T. Biewer, Sep. 20 th, 2004 NSTX Results Review of 11 Edge Ion Heating by Launched HHFW in NSTX T.M. Biewer, R.E. Bell, S. Diem, P.M. Ryan, J.R.
Measurement and Simulation of Dα Emission from First-Orbit Fast Ions and the Application to General Fast-Ion Loss Detection in the DIII-D Tokamak Nathan.
Charge Exchange Analysis Diagnostic Development
Visible Doppler Spectrometer for Edge Toroidal Rotation
Presentation transcript:

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting1 T. M. Biewer, R.E. Bell October 20 th, 2003 NSTX Physics Meeting Princeton Plasma Physics Laboratory ERD Observations in RF Heated Helium Plasmas

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting2 I got married.

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting3 Outline The Edge Rotation Diagnostic Ohmic, Helium Plasma –He (majority ion) and C (impurity ion) dynamics –Calculation of E r from force balance RF Heated Helium plasma –Cold component comparison to Ohmic plasma RF antenna is a BIG source of C at the edge –Hot component dynamics and implications Summary

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting4 The Edge Rotation Diagnostic Poloidal Chords Toroidal Chords 10 ms time resolution. 6 toroidal and 7 poloidal rotation chords covering 140 to 155 cm. Local E r =v  B-  p/eZn Does not require neutral beam. Sensitive to C III, C IV (impurity ions), and He II. Cold plasma broadens C III emission shell, resulting in possible  E r measurement. Edge rotation measurement complements main-CHERS. Poloidal Chords

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting5 Ohmic He Dischage Phil Ryan, et. al RF heating XP RF system shut down resulting in an Ohmic, He plasma I p ~500 kA, n e ~1.2x10 19 m -3, T e ~800 eV, B T ~0.44 T

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting6 Raw ERD data shows strong He, C light Fit the spectra (He or C) Amp.*Width Line brightness Emissivity (inversion) n z (with ADAS modeling) Width Apparent T i Center shift Apparent velocity Local velocity (inversion) ~ ~R ~ C III He II Poloidal views Toroidal views Edge most Core most Fiber

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting7 He II evolution at R=145 cm + is co-I p Apparent toroidal velocity and temperature

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting8 Modified Abel Inversion Inversion process: R.E. Bell, RSI 68, 1273 (1997). Poloidal radii from sightlines w/ EFIT due to strong plasma shaping He II peaks further in than C III consistent with its higher ionization potential (54.4 eV compared to 47.9 eV) Approximately equal Emissivities suggests that emission is essentially isotropic on the flux surface (during Ohmic He plasmas). He II (majority ion)C III (impurity ion) LCFS Tor. Pol. Tor. Pol.

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting9 He II dynamics R (cm) T i (eV) v (km/s) Good pol. & tor. agreement and w/ ionz. potential T i isotropic + tor. co-I p + pol. outboard mp. E r (kV/m) He II ion. Pot. He I ion. Pot. Time (sec) Tor., Pol., T e E r =vxB-  p/Zn LCFS

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting10 C III dynamics T C <T He ~60 eV not surprising R C >R He ~145 cm not surprising R (cm) T i (eV) v (km/s) E r (kV/m) C III ion. Pot. C II ion. Pot. Time (sec) Tor., Pol., T e LCFS

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting11 E r profile from He II and C III E r =vxB-  p/Zn Good agreement between the E r found from He II and that from C III q=2 radius Shape around LCFS similar to simulations for ASDEX-U. Kiviniemi PoP (2003) Other structure from TM islands? q=3 radius q=4 radius Probably not; no MHD activity.

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting12 Application of RF power Two shots from the same day of Phil Ryan’s RF heating XP Shot v I p 500 kA,500 kA B T 0.41 T,0.44 T P RF 4.3 MW,0 T e 1.7 keV,0.8 keV n e 2.0x10 19,1.2 x10 19 Ohmic RF heating

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting13 Two successive time frames clearly show the spectral consequences of 30 MHz HHFW heating (4.3 MW input) on the edge plasma. This effect is apparent in edge C (impurity) ions and He (bulk) ions. counts RF off Toroidal, r tan ~146 cm Pixel # (~ ) RF on RF off Poloidal, r tan ~146 cm Pixel # (~ ) RF on RF power heats edge ions Data is best fit with 2 Gaussian distribution function (hot and cold components).

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting14 HHFW RF Power heats edge ions 1G fit 2G high 2G low Time evolution of NSTX Shot shows that edge ion heating is well correlated with the application of 30 MHz HHFW power to the plasma.

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting15 He II cold component R (cm) T i (eV) v (km/s) Peak emission has moved outward. T i lower (but n e =2n e ), and is anisotropic (T pol =1.5T tor ) Tor. velocity appears more negative (anti-I p ) E r (kV/m) He II ion. Pot. He I ion. Pot. Time (sec) Tor., Pol., T e E r slightly more negative Rel. to Ohmic Ohmic Tor. Ohmic Pol. Ohmic Ohmic End of RF power LCFS

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting16 He II dynamics R (cm) T i (eV) v (km/s) Good pol. & tor. agreement and w/ ionz. potential T i isotropic + tor. co-Ip + pol. outboard mp. E r (kV/m) He II ion. Pot. He I ion. Pot. Time (sec) Tor., Pol., T e E r =vxB-  p/Zn

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting17 E r from He II and C III (cold) Ohmic v. RF heated The E r at the edge most region of the plasma (R>146 cm) is more negative during RF heated plasmas than during Ohmic. For R<146 cm the E r is similar (for the region measured) Implies that RF leads to ion loss at the edge of the plasma.  E r ~-5 kV/m RF on Ohmic

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting18 RF antenna sources C? E He for cold comp. of RF plasma ≈ E He of Ohmic E He for c.c. is balanced (tor~pol), as for E He of Ohmic E C of cold comp. of RF plasma >> E C of Ohmic Tor. E C >> Pol. E C for c.c. of RF plasma Collisions with edge C neutrals responsible for ion loss? He II (majority ion)C III (impurity ion) LCFS Tor. Pol. Tor. Pol. Ohmic

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting19 What about the Hot component?

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting20 Hot component of Hot component has an unequal distribution for both He and C, i. e. E pol >> E tor E pol : He h.c. >> c.c. ~ Ohmic, C h.c. ~ c.c. >> Ohmic E tor : He h.c. ~ c.c. ~ Ohmic, C h.c. ~ c.c. > Ohmic He II (majority ion)C III (impurity ion) LCFS Tor. Pol. Tor. Pol. Ohmic cold pol cold

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting21 A plasma dissected by Charge Exchange He + ~54 eV He 2+ ~max T i C+C+ ~24 eV C 2+ ~48 eV C 3+ ~65 eV C 4+ ~392 eV C 5+ ~490 eV C 6+ ~max T i He II C III C VI CHERS bkgnd C0C0 ~11 eV C 2+ ~11 eV He 0 ~max T i C 2+ ~11 eV C0C0 ~48 eV C 2+ ~11 eV C+C+ ~65 eV C 2+ ~11 eV C 2+ ~392 eV C 2+ ~11 eV C 3+ ~490 eV C 2+ ~11 eV C 4+ ~max T i C+C+ ~11 eV He 0 ~54 eV C+C+ ~11 eV He + ~max T i C+C+ ~11 eV C0C0 ~24 eV C+C+ ~11 eV C+C+ ~48 eV C+C+ ~11 eV C 2+ ~65 eV C+C+ ~11 eV C 3+ ~392 eV C+C+ ~11 eV C 4+ ~490 eV C+C+ ~11 eV C 5+ ~max T i CHERS signl C 3+ ~11 eV C0C0 ~65 eV C 3+ ~11 eV C+C+ ~392 eV C 3+ ~11 eV C 2+ ~490 eV C 3+ ~11 eV C 3+ ~max T i E pol : He h.c. >> c.c. ~ Ohmic, C h.c. ~ c.c. >> Ohmic E tor : He h.c. ~ c.c. ~ Ohmic, C h.c. ~ c.c. > Ohmic

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting22 More power leads to more heating From NSTX Shot to the applied RF power was increased. Empirically, T i increases as P RF Negative poloidal velocity is upwards on the outboard midplane. Negative toroidal velocity is opposite to the direction of I p.

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting23 Summary Applying power to the RF antenna coincides with large amounts of Carbon in NSTX –Antenna direct source? Effect greater near antenna (poloidal view). –Surface waves scouring the walls? Or why do we see anything in the toroidal view? This Carbon is useful as a Charge Exchange Diagnostic –There are hot ions in the edge. –Parametric decay of HHFW on He 2+ majority as heating mech. How does Carbon get hot? Collisions? Does running the antenna clean itself up? Need experiments with CHERS and antenna camera. Need modeling of edge plasma (CRM, MIST?).

T.M. Biewer, Oct. 20 th, 2003NSTX Physics Meeting24 Er from He II and CIII hot