Progress Toward Stabilization of Low Internal Progress Toward Stabilization of Low Internal Inductance Spherical Torus Plasmas in NSTX Inductance Spherical Torus Plasmas in NSTX S.A. Sabbagh 1 , J.W. Berkery 1 , J.M. Bialek 1 , S.P. Gerhardt 2 , R.E. Bell 2 , O.N. Katsuro-Hopkins 1 , J.E. Menard 2 , R. Betti 2,3 , L. Delgado-Aparicio 2 , D.A. Gates 2 , B. Hu 3 , B.P. LeBlanc 2 , J. Manickam 2 , D. Mastrovito 2 , J.K. Park 2 , Y.S. Park 1 , K. Tritz 4 1 Department of Applied Physics, Columbia University, NY, NY 2 Plasma Physics Laboratory, Princeton University, Princeton, NJ 3 University of Rochester, Rochester, NY 4 Johns Hopkins University, Baltimore, MD 52 nd APS DPP Meeting November 9 th , 2010 Chicago, Illinois College W&M Colorado Sch Mines Columbia U Comp-X General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U Sandia NL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Maryland U Rochester U Washington U Wisconsin Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI KBSI KAIST POSTECH ASIPP ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep U Quebec NSTX NSTX Supported by V1.8
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Progress Toward Stabilization of Low Internal Inductance Progress Toward Stabilization of Low Internal Inductance Spherical Torus Plasmas in NSTXSpherical Torus Plasmas in NSTX
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 2November 9th, 2010
NSTX is Addressing Global Stability Needs for Maintaining Low li, High Beta Plasmas for Fusion Applications
Motivation Achieve high N with sufficient physics understanding to allow
confident extrapolation to spherical torus applications (e.g. ST Component Test Facility, ST-Pilot plant, ST-DEMO)
Sustain target N of ST applications with margin to reduce risk Leverage unique ST operating regime to test physics models, apply
to ITER
Physics Research Addressed in this Talk Plasma operation at low plasma internal inductance (li) Resistive wall mode (RWM) destabilization at high plasma rotation Combined control systems to maintain <N>pulse at varied
RWM active control enhancements / advances at low li Multi-mode RWM spectrum in high N plasmas
NP9.00011 PengUP9.00006 Hawryluk
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 3November 9th, 2010
Future ST fusion applications will have high elongation, broad current profiles, high normalized beta
Broad current profiles (low li) consistent with high bootstrap current fraction; important to maintain high elongation
Demonstrating / understanding kink / RWM stability at low li is important
ST-Pilot (Qeng = 1)FNSF / ST-CTF
li = 0.47, = 3.2 R = 2.23 m, A = 1.7 Ip = 16 MA, Bt = 2.4T
N = 5.2, t = 30%
J. Menard, et al., IAEA FEC 2010 Paper FTP/2-2
Y.K.M. Peng, et al., PPCF 47 (2005) B263
Current Profile (MA/m2)
1 2 3 4
2.0
1.5
1.0
0.5
0.0R(m)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 4November 9th, 2010
RWM active stabilization coils
RWM poloidal sensors (Bp)
RWM radial sensors (Br)
Stabilizerplates
High beta, low aspect ratio R = 0.86 m, A > 1.27 Ip < 1.5 MA, Bt = 5.5 kG
t < 40%, N < 7.4
Copper stabilizer plates for kink mode stabilization
Midplane control coils n = 1 – 3 field correction,
magnetic braking of by NTV n = 1 RWM control
Varied sensor combinations used for RWM feedback 48 upper/lower Bp, Br
NSTX is a spherical torus equipped for passive and active global MHD control, application of 3D fields
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 5November 9th, 2010
Operation aims to produce sustained low li and high pulse-averaged N
Next-step ST fusion devices aim to operate at low li (high bootstrap current fraction > 50%) and high N
Focus on sustained low li and high <N>pulse
N vs. li (maximum values) N vs. li (pulse-averaged values)
N (
ma
xim
um)
ST-CTF
ST-DEMO (ARIES-ST)
ST-CTF
< N
>p
ulse
ST-Pilot ST-Pilot
ST-DEMO (ARIES-ST)
Recent years with “routine” n = 1 RWM feedback (red)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 6November 9th, 2010
0
1
2
3
4
5
6
7
8
0.0 0.2 0.4 0.6 0.8
Operation aims to produce sustained low li and high pulse-averaged N
N vs. li (maximum values)
N
N/li is a common parameter to evaluate global stability Kink/ballooning and
RWM stability
Significant increase in maximum N/li Upper limit now
between 13 - 14
li
N/li 13 12 11 1014
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 7November 9th, 2010
Operation aims to produce sustained low li and high pulse-averaged N
N vs. li (maximum values)
N
N/li is a common parameter to evaluate global stability Kink/ballooning and
RWM stability
Significant increase in maximum N/li Upper limit now
close to experimental value ~ 30 Hz ITER scenario IV multi-mode spectrum
Significant spectrum for n = 1 and 2
Bn from wall, multi-mode responseBn RWM multi-mode composition
ideal eigenmode number
Bn
ampl
itude
(ar
b)
t = 0.655s
mode 1
mode 2
2.01.00.0R(m)
1.0
-1.0
Z(m
)
2.0
0.0
-2.0
mode 3
133775
mode
1
mode
3
mode
2
Unstable
Stabilized by rotation
BP9.00059 J. Bialek, et al.; see poster for detailmmVALEN code
N = 6.1
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 28November 9th, 2010
NSTX is Addressing Global Stability Needs Furthering Steady Operation of High Performance ST Plasmas
Success in producing, and stabilizing plasmas with reduced li
Approaching conditions of ST fusion applications
RWM instability observed at intermediate plasma rotation correlates with kinetic stability theory Suggests the need for rotation control in future ST devices; evaluation of
energetic particle (EP) stabilization
Initial analysis of low li plasmas indicates similar stability dependence on
n = 1 RWM feedback control combined with N feedback control shows stability and regulation of high N at varied plasma rotation levels
Compatible with plasma rotation control by non-resonant 3D fields
New RWM state space controller sustains high N plasma
Potential for greater flexibility of RWM control coil placement in burning plasma devices
Computed multi-mode RWM spectrum at high N with 3D conducting structure shows significant amplitude in higher order eigenmode
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 29November 9th, 2010
Backup and Poster Slides
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 30November 9th, 2010
RWM state space controller sustains otherwise disrupted plasma caused by DC n = 1 applied field
n = 1 DC applied field Simple method to
generate resonant field amplication
Can lead to mode onset, disruption
RWM state space controller sustains discharge With control, plasma
survives n = 1 pulse n = 1 DC field
reduced Transients controlled
and do not lead to disruption
NOTE: initial run – gains NOT optimized
00.20.40.60.81.01.2
amperes
0123456
-
0246810
Tesla
0100200300400500
amperes
0 0.2 0.4 0.6 0.8 1.0sec
024681012
*
140025140026
Shots:
140025140026
Control applied
Control not applied
N
IRWM-4 (kA)
~q=2 (kHz)
t(s)
Bpn=1 (G)
Ip (kA)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 31November 9th, 2010 31
ITER Advanced Scenario IV: RWM just reaches marginal stability by energetic particles with N = 3
Energetic particle (EP) effect Alpha particles are required
for RWM stabilization at all Near RWM marginal stability
at ITER expected /total = 0.19 at =
Polevoi
MISK stability code
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 32November 9th, 2010
ITER Advanced Scenario IV: multi-mode RWM spectra computation shows significant ideal eigenfunction amplitude for several components
Z(m
)
-4
-2
0
2
4
6
4 6 8 10
ITERBnormalPLOTS2010
Z 1.00Z Bn#1@0 1Z Bn#3@0 1Z Bn#5@0 1
Z 1
.00
R 1.00
n = 2.6530 n=1
DDSO.EQDSK_ITER1.00S
-4
-2
0
2
4
6
4 6 8 10
ITERBnormalPLOTS2010
Z 1.40Z Bn#1@0 1Z Bn#3@0 1Z Bn#5@0 1
Z 1
.40
R 1.40
n = 3.9170 n=1
DDSO.EQDSK_ITER1.40S
N = 3.92n = 1
N = 2.65n = 1
-4
-2
0
2
4
6
4 6 8 10
ITERBnormalPLOTS2010
n=2 Z 1.40n=2 Z Bn#1@0 1n=2 Z Bn#3@0 1n=2 Z Bn#5@0 1
n=
2 Z
1.4
0
n=2 R 1.40
n = 3.9170 n=2
DDSO.EQDSK_ITER1.40S
N = 3.92n = 2
mode 1
4
-2
6
0
-4
2
R(m)4 6 8 10
Z(m
)
4
-2
6
0
-4
2
R(m)4 6 8 10
Z(m
)
4
-2
6
0
-4
2
R(m)4 6 8 10
0 3 9 126 15
1.0
0.8
0.6
0.4
0.2
0.0
mode 2mode 3
mode 1mode 2mode 3
mode 1mode 2mode 3
ideal eigenmode number
Bn
ampl
itude
(ar
b)
Multi-mode spectrum
N = 2.65n = 1
0 3 9 126 15
1.0
0.8
0.6
0.4
0.2
0.0
ideal eigenmode number
mmVALEN
0 3 9 126 15
1.0
0.8
0.6
0.4
0.2
0.0
ideal eigenmode number
Multi-mode
spectrum
Multi-mode
spectrum
N = 3.92n = 1
N = 3.92n = 2
Nno-wall = 2.5
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 33November 9th, 2010
ABSTRACT
Steady-state spherical torus plasmas for fusion applications, such as a component test facility or demonstration power plant, target operation with high non-inductive current fraction. These broad current profile targets have low values of plasma internal inductance, l i, less than 0.4, near to the lower end of present NSTX operation. A key significance of this operation is that it approaches the purely current-driven ideal kink limit, which by definition exceeds the no-wall stability limit for all values of plasma normalized pressure (beta). In this regime, passive or active kink and resistive wall mode (RWM) stabilization is critical. Experiments on NSTX have recently approached this condition, evidenced by a significant reduction of the n = 1 no-wall stability limit computed by DCON. This limit drops from normalized beta of 4.2 – 4.6 at l i ~ 0.6, to 3.4 at li ~ 0.5, to below 2.8 for li ~ 0.4. Nevertheless, passive and active RWM control has produced high toroidal beta up to 28 percent, and normalized beta up to 6.5 (nearly double the no-wall limit), closely following a record normalized beta to li ratio of 13 between li = 0.4 - 0.5. Non-inductive current fraction reaches 0.5 in these high normalized current plasmas. However, the disruption probability of these plasmas increases significantly, with about half of the discharges suffering terminating instabilities. Alteration of n = 1 RWM control system parameters, plasma rotation profile, and the role of beta feedback is examined to potentially improve mode stability. Ion precession drift and bounce frequency resonance stabilization is examined for these plasmas and compared to the identified stabilization reduction at intermediate plasma rotation and higher l i [1,2].
[1] J.W. Berkery, et al., Phys. Rev. Lett. 104, 035003 (2010)
*Work supported by U.S. DOE Contracts DE-FG02-99ER54524 and DE-AC02-09CH11466.
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 34November 9th, 2010
Work slides
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 35November 9th, 2010
Slide ToDos
To Do Update words on database slides Add n = 1 no-wall limit “extension” on n = 1 line in database plot Add database slide showing the results of IMPROVEMENTS to
control systems, etc. – can be an intro to the next sections of talk. Illustrate reduced disruptivity here best you can!
• Think about how best to do this in the short-term
• Use XP1023 runs from (some 7/29), 8/3, 8/19, 9/24, other runs, fiducials
• NOTE: Runs on 4/13 and 4/15 mostly were lower betaN Add database slide(s) as time allows (<betaN>, <BetaT> vs. pulse) Update Bp feedback phase slide Update (combine?) Br gain / phase variation slide Include key PHYSICS of the change in RWM mode dynamics in the
waveform slides (see EXCEL spreadsheet for this) Update VALEN model of 3d conducting structure
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 36November 9th, 2010
ABSTRACT (update to include new control/stability, RWMSC)
Steady-state spherical torus plasmas for fusion applications, such as a component test facility or demonstration power plant, target operation with high non-inductive current fraction. These broad current profile targets have low values of plasma internal inductance, l i, less than 0.4, near to the lower end of present NSTX operation. A key significance of this operation is that it approaches the purely current-driven ideal kink limit, which by definition exceeds the no-wall stability limit for all values of plasma normalized pressure (beta). In this regime, passive or active kink and resistive wall mode (RWM) stabilization is critical. Experiments on NSTX have recently approached this condition, evidenced by a significant reduction of the n = 1 no-wall stability limit computed by DCON. This limit drops from normalized beta of 4.2 – 4.6 at l i ~ 0.6, to 3.4 at li ~ 0.5, to below 2.8 for li ~ 0.4. Nevertheless, passive and active RWM control has produced high toroidal beta up to 28 percent, and normalized beta up to 6.5 (nearly double the no-wall limit), closely following a record normalized beta to li ratio of 13 between li = 0.4 - 0.5. Non-inductive current fraction reaches 0.5 in these high normalized current plasmas. However, the disruption probability of these plasmas increases significantly, with about half of the discharges suffering terminating instabilities. Alteration of n = 1 RWM control system parameters, plasma rotation profile, and the role of beta feedback is examined to potentially improve mode stability. Ion precession drift and bounce frequency resonance stabilization is examined for these plasmas and compared to the identified stabilization reduction at intermediate plasma rotation and higher l i [1,2].
[1] J.W. Berkery, et al., Phys. Rev. Lett. 104, 035003 (2010)
*Work supported by U.S. DOE Contracts DE-FG02-99ER54524 and DE-AC02-09CH11466.
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 37November 9th, 2010
NSTX is Addressing Global Stability Needs for Maintaining Long-Pulse, High Performance Plasmas
Motivation Achieve high N with sufficient physics understanding to allow
confident extrapolation to spherical torus applications (e.g. ST Component Test Facility, ST-Pilot plant, ST-DEMO)
Sustain target N of ST applications with margin to reduce risk Leverage unique ST operating regime to test physics models, apply
to ITER
Physics Research Addressed Plasma operation at low plasma internal inductance, li Resistive wall mode (RWM) destabilization at high plasma rotation RWM active control enhancements / advances at low li Combined control systems to maintain <N>pulse at varied
Multi-mode RWM spectrum in high N plasmas
Papers: ppppppppp
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 38November 9th, 2010
Common Features of Present & Future STs• High- and strong shaping.•N values at or above the no-wall limit. • Bootstrap fractions ≥50%. • Confinement ≥ H-mode scaling.• Comprehensive shape, profile and stability control.
Configuration Specific Features• Range of normalized currents.• Wide range of NBCD fractions.• Wide range of normalized
densities.
N
li(1)
IN
fGW
fBS
fNBCD
H98
NSTX
2.6
5.7
0.55
2.5
0.8
0.54
15
1.
NSTX-U
2.7
5.7
0.65
2.1
0.7
0.7
30
1.2
NHTX
3
5
0.6
3
0.45
0.7
0.3
1.3
ST-CTF1
3.1
4-6
0.35
4.5
0.28
0.5
0.5
1.5
ST-Demo2
3.5
7.5
0.25
6.7
0.8
0.96
0
1.3
S.P. Gerhardt (NSTX PAC-27)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 39November 9th, 2010
NSTX is Addressing Global Stability Needs Furthering Steady Operation of High Performance Plasmas
RWM instability observed at intermediate correlates with kinetic stability theory
n = 1 RWM, N feedback control maintains high N at varied using n = 3 NTV profile modification
Stronger NTV braking at reduced E
Initial success of RWM state space controller at high N
Multi-mode RWM physics spectrum
profile control
Sufficient EP stabilization
Potential control compatibility
profile control impact
More flexibility of control coil placement
Determine RWM control impact
Sufficient EP stabilization needed at low
Potential control at low if EP stabilization insufficient
Further examine NTV at low
More flexibility of control coil placement
Determine RWM control impact
Physics addressed Future STs(NBI-driven, high )
ITER advanced scenarios (low )
Implications for
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 40November 9th, 2010
NSTX Database Plots – v2
BetaN vs. li (maximum values)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 41November 9th, 2010
NSTX Database Plots
BetaN vs. li (pulse-averaged values)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 42November 9th, 2010
NSTX Database Plots – v2 – li08
BetaN vs. li (maximum values)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 43November 9th, 2010
NSTX Database Plots
BetaN vs. li (maximum values)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 44November 9th, 2010
NSTX Database Plots
BetaN vs. li (pulse-averaged values)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 45November 9th, 2010
Pressure peaking factor remains an essential component of high N operation
Broad pressure profile needed to maintain high N stability limit
•BetaN vs. Pressure peaking plot here
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 46November 9th, 2010
Characterization of Disruption Stats and Wtot variation here
Show improved disruption statistics and Wtot variation
Disruption Statistics
Wtot variation
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 47November 9th, 2010
Update this slide (use <betaN>, <betaT>, <betaN/li>
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 48November 9th, 2010
MISK calculations show reduced stability in low li target plasma as is reduced, RWM instability is approached
Stability evolves li increases in time as RWM
instability is approached, but remains low (li = 0.42)
MISK computation shows plasma to be stable at time of minimum li
Region of reduced stability vs. found before RWM becomes unstable (li = 0.49)
• Co-incident with a drop in edge density gradient – reduces kinetic stabilization
MISK application to ITER (advanced scenario IV) RWM unstable at expected rotation Only marginally stabilized by
alphas at N = 3
140132
t = 0.704s
stable
unstable
- BP9.00057 J. Berkery, et al.- Also, see poster for detail
experiment
RWM stability vs. (contours of w)
2.0
1.0
/exp
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 49November 9th, 2010
(Bp Feedback Phase Slide): Adjusting Bp sensor feedback phase around 180 degrees led to long-pulse, low li, high N/li
139347139515139516139517
Steady, high N/li Between 12
– 13
Low li state retained
180 deg202.5 deg157.5
Bpn = 1 (G)
Ip (MA)
N
li
N/li
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 50November 9th, 2010
0123456
0123456
-600-400-200
0200400600
02468101214
0 0.2 0.4 0.6 0.8 1.0 1.2sec
051015202530
135468135513
Shots:
N feedback combined with n = 1 RWM control to reduce N fluctuations at varied plasma rotation levels
Prelude to control Reduced by n
= 3 braking is compatible with N FB control
Steady N established over long pulse independent of
over a large range
Radial field sensors added to n = 1 feedback (2010) Full sensor set
further reduces n = 1 amplitude, improves control
135468135513
0.80.4 0.6 1.0 1.2t(s)
0.20.0
N
2
46
I RW
M-6 (
kA) 0.6
0
2
46
-0.6
PN
BI (
MW
) ~
q=
2
(kH
z) c
ore
(kH
z)
48
12
30
10
n = 3 brakingn = 1 feedback
0
20
0
q ~ 2 rotation
Core rotation
n = 3 errorcorrection
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 51November 9th, 2010
VALEN comparisons to NSTX PID feedback
(Probably won’t be enough time for this – perhaps a bullet at most, if the results are in)
Show that new PID feedback settings are consistent with theory Bp sensor feedback is consistent with (old) VALEN model
Consistent with new VALEN model? BR sensor feedback is consistent with VALEN model
VALEN comparisons
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 52November 9th, 2010
Include more RWM State-space controller results
New results / analysis / slides (possible ToDos) Improved diagram for feedback phase (show more phases?) Illustration of changing gains in experiment
Completed ideas included in talk Theoretical stability predictions Illustration of changing number of states in experiment
• Done for observer
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 53November 9th, 2010
New RWM state space controller sustains high N plasma
Balancingtransformation
~3000+ states
Full 3-D model
…
RWMeigenfunction(2 phases,
2 states)
)ˆ,ˆ( 21 xx 3x̂ 4x̂ Nx̂truncate
State reduction (< 20 states)
State space feedback with 12 states
Controller can compensate for wall currents Including mode-induced current Examined for ITER
Successful initial experiments Suppressed disruption due to n
= 1 applied error field Best feedback phase produced
long pulse, N = 6.4, N/li = 13
- device R, L, mutual inductances- instability B field / plasma response- modeled sensor response
Katsuro-Hopkins, et al., NF (2007) 1157
00.20.40.60.81.01.2
amperes
01234567
-
0246810
Tesla
0100200300400500
amperes
0 0.2 0.4 0.6 0.8 1.0 1.2 1.4sec
02468
140037140035
Favorable FB phaseUnfavorable feedback phase
N
IRWM-4 (kA)
~q=2
(kHz)
Bpn=1 (G)
Ip (kA)
0.80.4 0.6 1.0 1.2t(s)0.20.0 1.4
1.00.5
06420840
400200
0
840
12
00.20.40.60.81.01.2
amperes
01234567
-
0246810
Tesla
0100200300400500
amperes
0 0.2 0.4 0.6 0.8 1.0 1.2 1.4sec
02468
140037140035
Favorable FB phaseUnfavorable feedback phase
N
IRWM-4 (kA)
~q=2
(kHz)
Bpn=1 (G)
Ip (kA)
0.80.4 0.6 1.0 1.2t(s)0.20.0 1.4
1.00.5
06420840
400200
0
840
12
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 54November 9th, 2010
RWM State Space Control – Theoretical Performance
text
Low N
input
2, 12 states
High N
input
Control at low plasma rotation
4.0 N4.5 5.0 5.5 6.0 6.5 7.0 7.5
100
101
102
103
104
(1
/s)
Proportional gain control limit
Passive growth
Idea
l Wal
l Lim
it
State
space
controller
(low input)
(high
input)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 55November 9th, 2010
RWM State Space Control – Theoretical Performance
text
Low N
input
2, 12 states
High N
input
Control at low plasma rotation
ideal wall limitpassive growthinput 1: 12 statesinput 2: 12 states
4.0 N4.5 5.0 5.5 6.0 6.5 7.0 7.5
100
101
102
103
104
(1
/s) Proportional gain
control limit
Passive growth
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 56November 9th, 2010
Organization / Outline slides
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 57November 9th, 2010
Specifics
Talk constraints 25 minutes talk + 5 minutes discussion (8 more mins. than IAEA) 2010 IAEA had 14 slides (was tight): 1.214 min/slide Estimate 20 - 21 slides, plus backup 2001: 20 slides (simple slides – ok length) 2006: 16 slides (good length)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 58November 9th, 2010
Outline - Topics
Outline - Topics Motivation – ST-CTF, ST Pilot Plant, ITER
• Maintenance of high beta state, with miminal fluctuation
• Active control needs to meet needs of high neutron flux devices (coils further back from device, or shielded)
• Outline: include both passive and active stabilization physics – and keys for how they extrapolate to future devices
Example of broad current profile target plasma (ST-CTF or ST-Pilot; NSTX-U) Illustration of stability space (li, BetaN) showing schematic limits
• Show NSTX database, with schematic limits superposed
• Show position of ST-CTF, ST-Pilot, NSTX-U, etc. on this plot
Illustration of stability space (li, BetaN) – ZOOMED in to low li
• Show recent low li plasmas as a different color on this plot Might be effective as an overlay plot, depending on where recent data / stable data lies on diagram
• Separate out stable plasmas vs. disruptions if possible
Ideal no-wall stability limit computation for trajectories on (li, BetaN) diagram
• Give margin over the n = 1 no-wall limit
Progress towards maintaining steady plasma stored energy at high beta
• Initial runs (2009) – high disruption probability – show statistics in bullets / stacked bar chart / plots on diagram
• Long-pulse shots at high betaN ELM-free, and no large Li buildup, no n = 1 rotating mode (with lithium)
• Improved PID feedback control (Bp and Br sensor results)
• state-space control
• beta feedback – at varied rotation
• Figures of merit: pulse avg betaN, std deviation
Passive stabilization physics
• Rotation and EP effects - (need equilibria for most recent results)
• Comparison of higher li to low li plasmas – difference in physical interpretation?
RWM control at high beta; considerations for burning plasma devices
• Multi-mode RWM physics, observations in NSTX
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 59November 9th, 2010
Title page Motivation – ST-CTF, ST Pilot Plant, ITER
• Maintenance of high beta state, with minimal fluctuation
• Active control needs to meet needs of high neutron flux devices (coils further back from device, or shielded)
• Outline: include both passive and active stabilization physics – and keys for how they extrapolate to future devices
Example of broad current profile target plasma (ST-CTF or ST-Pilot; NSTX-U) Low li plasma with RWM instability – 137722, or other (use IAEA slide directly? Good segway to MISK results) Illustration of stability space (li, BetaN) showing schematic limits
• Show NSTX database, with schematic limits superposed
• Show position of ST-CTF, ST-Pilot, NSTX-U, etc. on this plot
Illustration of stability space (li, BetaN) – ZOOMED in to low li
• Show recent low li plasmas as a different color on this plot Might be effective as an overlay plot, depending on where recent data / stable data lies on diagram
• Separate out stable plasmas vs. disruptions if possible
Ideal no-wall stability limit computation for (li, betaN) trajectories on (li, betaN) diagram
• Give margin over the n = 1 no-wall limit
Progress towards maintaining steady plasma stored energy at high beta
• Initial runs (2009) – high disruption probability – show statistics in bullets / stacked bar chart / plots on diagram
• Long-pulse shots at high betaN ELM-free, and no large Li buildup, no n = 1 rotating mode (with lithium)
Improved PID feedback control (Bp and Br sensor results) state-space control beta feedback – at varied rotation Figures of merit: pulse avg betaN, std deviation
(Continued on next page)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 60November 9th, 2010
• Rotation and EP effects - (need equilibria for most recent results)
• Comparison of higher li to low li plasmas – difference in physical interpretation? Multi-mode RWM physics, observations in NSTX Multi-mode RWM physics, implications for ITER Summary (use format showing implications for future STs, ITER - worked well at IAEA)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 61November 9th, 2010
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 62November 9th, 2010
Title page Motivation – ST-CTF, ST Pilot Plant, ITER
• Have outline on this slide, or as a separate (very simple) slide?? NSTX device / geometry slide RWM instability / RFA at high plasma rotation
• Instability at intermediate and high rotation – low rotation “threshold” not adequate for stability Consequences for an ST-CTF / Pilot Plant, and ITER
• Show RFA results here from recent XP1020 as well Passive stabilization physics – NSTX and MISK code
• Rotation and collisionality effects – contour plot
• Clearly state physics implications for ITER and ST-CTF – importance of new results vs. old (low) crit.rotation Unification of devices using new model (MISK)
• DIIII-D: comparison of energetic particle fraction / stability margin due to EPs vs. NSTX
• JT-60U: (mention in a bullet on this slide)
• ITER: BULLET HERE – advetrize full slide that will appear on poster Progress towards maintaining steady plasma stored energy at high beta
• As default, use slide with n = 3 EFC, n = 1 FB, betaN control
• Figures of merit: pulse avg. betaN, std. deviation The role of NTV physics at low nu_i/OmegaE, and low OmegaE - Superbanana plateau regime in NSTX
• Low OmegaE results – superbanana plateau in NSTX
• Optional: results for NTV offset rotation, change in rotation damping vs. collisionality, etc. RWM state space control
• RESERVE the theoretical growth rate plot for the POSTER and PAPER
• Need to DEFINE state space control / NSTX especially well suited to test / connect to ITER
• First experimental results RWM control at high beta; considerations for burning plasma devices (I)
• Multi-mode RWM physics, expectations in NSTX – NSTX mmVALEN mode spectrum RWM control at high beta; considerations for burning plasma devices (II)
• Addition of differential rotation – change in VALEN multi-mode spectrum, rot. speed; observations in NSTX Summary
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 63November 9th, 2010
Some IAEA FEC 2010 slides follow
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 64November 9th, 2010
NSTX is Addressing Global Stability Needs for Maintaining Long-Pulse, High Performance Plasmas
Motivation Achieve high N with sufficient physics understanding to allow
confident extrapolation to spherical torus applications (e.g. ST Component Test Facility, ST-Pilot plant, ST-DEMO)
Sustain target N of ST applications with margin to reduce risk Leverage unique ST operating regime to test physics models, apply
to ITER
Physics Research Addressed Resistive wall mode (RWM) destabilization at high plasma rotation RWM active control advancements Combined control systems to maintain <N>pulse at varied
Physics of 3D fields to control plasma rotation Multi-mode RWM spectrum in high N plasmas
Papers: ppppppppp
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 65November 9th, 2010
NSTX is Addressing Global Stability Needs Furthering Steady Operation of High Performance Plasmas
RWM instability observed at intermediate correlates with kinetic stability theory
n = 1 RWM, N feedback control maintains high N at varied using n = 3 NTV profile modification
Stronger NTV braking at reduced E
Initial success of RWM state space controller at high N
Multi-mode RWM physics spectrum
profile control
Sufficient EP stabilization
Potential control compatibility
profile control impact
More flexibility of control coil placement
Determine RWM control impact
Sufficient EP stabilization needed at low
Potential control at low if EP stabilization insufficient
Further examine NTV at low
More flexibility of control coil placement
Determine RWM control impact
Physics addressed Future STs(NBI-driven, high )
ITER advanced scenarios (low )
Implications for
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 66November 9th, 2010
Rotation profile at RWM marginal stability altered by varying energetic particle content
Ip, Bt altered keeping q fixed in experiment
Fast ion density increases with increased Ip
Indicated by fast ion D diagnostic
Range of TRANSP fast/tot 17% - 31%
General reduction of RWM marginal profile as Ip increased
Rotation profiles at marginal stability
Relative fast ion density profiles
J.W. Berkery, et al., Phys. Plasmas 17 (2010) 082504
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 67November 9th, 2010 6767
Model of kinetic modifications to ideal stability can unify RWM stability results between devices
NSTX Less EP stability: RWM can cross
marginal point as is varied
DIII-D More EP stability (~ 2x NSTX):
RWM stable at all
RWM destabilized by events that reduce EP population
ITER (advanced scenario IV) RWM unstable at expected rotation Only marginally stabilized by alphas
at N = 3
Stability overpredicted with EPs – model development continues Improve NBI anisotropic distribution Examine effects originally thought
small
H. Reimerdes, et al., paper EXS/5-4
NSTX
DIII-D
calculation with EPs
unstable
thermal ions
energetic particles (EPs)
NSTXDIII-D (rescaled)
See poster (EXS/5-5)γτw ~ 0.1
NSTX
experiment
See poster (EXS/5-5)
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 68November 9th, 2010
Additional Slides
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 69November 9th, 2010
NSTX is Addressing Global Stability Needs Furthering Steady Operation of High Performance Plasmas
RWM instability observed at intermediate plasma rotation correlates with kinetic stability theory Theory of kinetic modifications to ideal stability may unify RWM stability
results between devices
ITER advanced scenario 4 requires EP stabilization at expected
n = 1 RWM feedback control combined with new N feedback control shows regulation of high N at varied plasma rotation levels
Compatible with plasma rotation control by non-resonant 3D fields
Stronger non-resonant NTV braking observed at reduced E
New RWM state space controller sustains high N plasma
Potential for greater flexibility of RWM control coil placement for burning plasma devices
Computed multi-mode RWM spectrum at high N shows significant amplitude in higher order modes
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 70November 9th, 2010
Energetic particles are stabilizing to RWM; computed effect is smaller in NSTX when compared to DIII-D
Smaller energetic particle (EP) fraction in NSTX Less stability due to EPs
Scaled Wk from MISK shows larger stabilization effect due to EPs in DIII-D
H. Reimerdes, et al., paper EXS/5-4
NSTXNSTX 52nd APS DPP Meeting: Progress Toward Stabilization of Low li Spherical Torus Plasmas in NSTX (S.A. Sabbagh, et al.) 71November 9th, 2010
Advancements in MISK stability model continue
Electrostatic effect Additional anisotropic term
Centrifugal destabilization Other possibilities:
[B. Hu et al., Phys. Plasmas 12, 057301 (2005)]
In addition to present anisotropy effects on δWK, when f is anisotropic an additional term arises that is proportional to :
– Inclusion of plasma inertia term in the dispersion relation
– Effect of poloidal rotation on ωE (small)– Use of a Lorentz collisionality model instead of
current ad-hoc inclusion of collisionality
The electrostatic component of the perturbed distribution function contributes to δW. (expected to be small).
This fluid force term is usually neglected, but it is always destabilizing, and could be important if the plasma rotation Mach number is significant, or for alpha particles rotating at higher frequency ~ ω*α.