the toroidal current is consistent with numerical estimates of bootstrap current the measured...
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0 2 4 6 8 10 12 14 16-2
0
2
4x 10
-4
B
(T)
0 2 4 6 8 10 12 14 16-2
0
2
4x 10
-4
B
(T)
V3FIT Itor
= 0
Exp. t = 10. ms
0 2 4 6 8 10 12 14 16-2
0
2
4
6
x 10-4
B
(T)
0 2 4 6 8 10 12 14 16-5
0
5x 10
-4
Br (
T)
Poloidal Station #
V3FIT Itor
= 0
V3FIT Itor
= IBOOTSJ
Exp. t = 10. msExp. t = 50. ms
0 2 4 6 8 10 12 14 16-5
0
5
10x 10
-4
B
(T)
0 2 4 6 8 10 12 14 16-5
0
5x 10
-4
Br (
T)
Poloidal Station #
V3FIT Itor
= 0
V3FIT Itor
= IBOOTSJ
Exp. t = 10. msExp. t = 50. ms
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10
500
1000
P (
Pa)
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1-50
0
50
100
(kA
/ m
2 )
JBS
. B
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10.95
1
1.05
1.1
s = 2
iota
with bootstrap current (vacuum)
• The toroidal current is consistent with numerical estimates of bootstrap current• The measured magnetic diagnostic signals match predictions of V3FIT
• Comparisons with and without toroidal bootstrap current show agreement• Helical nature of Pfirsch-Schlüter current in HSX has been confirmed
• Future modeling and measurement• Temporal evolution of toroidal current will be studied – Poloidal flux diffusion• Effects of toroidal current on rotational transform will be studied• Configuration Flexibility: HSX can alter the magnetic spectrum with a set of auxiliary coils• Mirror: The helical symmetry is spoiled by introducing (n,m) = (4,0) component (and harmonics) into the magnetic spectrum, affecting the equilibrium and bootstrap currents• Well/Hill: Rotational transform profile may be raised/lowered, adjusting the location of the = 1 resonant surface
0 20 40 60 800
100
200
300
400
500
600
time (ms)
I tor
(Am
ps)
EC
H tu
rnoff
0
50
100
150
200
250
S.E
. (J
oule
s); n
e (10
11 c
m-3
)
0
50
100
150
200
250
0 10 20 30 40 50 60 700
100
200
300
400
500
600
700
800
rise
= 39.4125 ms I = 708.1735 A
t0 = 4.7003 ms
I tor
(Am
pere
s)
EC
H turn
off
T.S
. Laser
time (msec)
Itor
Measured
Central ne (line average)
Stored Energy
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10
500
1000
1500
2000
2500
3000
T e (e
V)
0 100 200 300 400 500 6000
200
400
600
800
1000
Boostrap Current -- BOOTSJ (A)
I tor
Itor
@ t = ECH Off
Extrapolated ISS
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 110
-3
10-2
10-1
100
101
102
* e
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 10
1
2
3
4
5
6
7
8
9
10
n e (1
012cm
-3)
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 110
-2
10-1
100
101
Magnetic
Diff
usiv
ity (m2 /s
)
• The Helically Symmetric eXperiment has• Quasi-Helically Symmetric axis: (n,m)=(4,1)• No toroidal curvature
• The Pfirsch-Schlüter current • Rotates with toroidal angle• Is reduced by a factor of compared to a conventional stellarator
• The bootstrap current• Is in opposite direction than that of a tokamak• Reduces the rotational transform in HSX
• VMEC• Calculates free-boundary MHD Equilibrium • Inputs are measured Te & ne profiles and
assumed Ti & ni (Zeff ≈ 1)• BOOTSJ
• Calculates bootstrap current profile from VMEC results. Results may be input back into VMEC as toroidal current profile.
• V3FIT• Computes response function for diagnostic coils• Expected magnetic signals are computed from response functions and VMEC output
• BOOTSJ calculates the bootstrap current; Assumes LMFP regime• BOOTSJ provides an upper limit to the bootstrap current• The toroidal current rises throughout the majority of the shot
• Steady state reached only in coldest plasmas• Decaying exponential growth is observed in many cases:
projections are based this model
Measurement of the Pfirsch-Schlüter and Bootstrap Currents in HSX
HSX Magnetics and HSX Magnetics and Computational ModelingComputational Modeling
J.C. Schmitt, J.N. Talmadge, P.H. Probert, S.F. Knowlton*, D.T. AndersonHSX Plasma Laboratory, Univ. of Wisconsin – Madison, WI USA *Physics Department, Auburn Univ. – Auburn, AL USA
Summary + Future DirectionsSummary + Future Directions
Pfirsch-Schlüter CurrentPfirsch-Schlüter CurrentOperating Parameters Operating Parameters & Diagnostics& Diagnostics
Bootstrap CurrentBootstrap Current
Numerical Model and Measurement
• B0 = 1 Tesla• 50 kW ECR Heating (1st Harmonic)
• 10-chord Thomson Scattering• Te(ρ) and ne(ρ) profiles
• Rogowski coil – External • Toroidal current• Low-frequency response
• dB/dt triplet array – External• MHD and bootstrap currents• Low-frequency response• Poloidal and toroidal measurements
• The Pfirsch-Schlüter current exhibits dipole behavior and rotates with the |B| contours
Temporal Evolution of Currents in HSXTemporal Evolution of Currents in HSX
• Majority of HSX plasmas are in long mean free path (LMFP) regime• Magnetic diffusivity varies across the confinement volume
16
Poloidal Station #16
2
1
1
2
BOOTSJ: 478 A
• Diagnostic signals and toroidal current evolution• t = 10. ms: MHD equilibrium established, bootstrap current still small• t = 50. ms: ECH turn-off, bootstrap current has grown to 450 A
• The diagnostic signals agree well with the V3FIT numerical results• Toroidal current is still evolving – Radial profile information is not yet known
VMEC equilibrium, JBS=JBOOTSJ
effTe2/1* Rqvh
hee
0
||
• The bootstrap current is the upper limit for the measurements to date• Projected steady state values exceed bootstrap current estimate
• Decaying exponential growth is not appropriate for most cases – may overestimate steady state value
1/2 FP
1/6 FP
Poloidal Rotation of Null Point in Bθ
50 kW ECRH heated plasma
Profiles obtained during resonance heating location scan
TorteItI /1
3
11 mN
• Special thanks to Steve Knowlton and the V3FIT team
HSX Vacuum Vessel and Diagnostic Coils
Off-axis ECRH
Near-axis ECRH
JPS
1/2 FP
1/2 FP 1/6 FP
1/6 FP
49th Annual Meeting of the Division of Plasma Physics, November 12-16, 2007, Orlando, Florida
Offset in measured Bθ due to toroidal bootstrap current