Measurements of Heat-flux Footprints at the Inner Divertor Target … · 2017. 11. 9. · J....
Transcript of Measurements of Heat-flux Footprints at the Inner Divertor Target … · 2017. 11. 9. · J....
APS-DPP Milwaukee, WI, Oct. 23, 2017
Research was supported by US DOE OFES
Measurements of Heat-flux Footprints at the Inner Divertor Target of Alcator C-Mod J.L. Terry, D. Brunner, B. LaBombard, S.M. Wolfe
Background & motivation for interest in I-mode power exhaust
• I-mode is an attractive stationary regime of high energy confinement (H-mode-like energy confinement)
• L-mode particle and impurity confinement • No ELMs
• We seek to measure the heatflux widths (λq) at the inner target and see how they compare with those on the outer target and the “Eich scaling” for λq (which is based on outer target λq in attached H-mode plasmas)
MAST J. Harrison
Whyte NF (2010) & Hubbard IAEA (2012)
Background & motivation for interest in I-mode power exhaust
• Exhaust power handling in I-mode remains a challenge (as it does for H-mode plasmas)
• Lower densities and low impurity density result in lower Prad and higher Pouter target(compared to H-mode)
• We have tried to detach I-mode plasmas, so far without success
• Fewer ideas for power handling on inner divertor than ideas for outer divertor power handling (e.g. Super X or X-point Target or Li Vapor Box Div.)
• Near-DN should provide a way to mitigate power to inner target • We also seek to measure the heat-flux on the inner target in near-DN
configurations and examine the power sharing between inner and outer targets
MAST J. Harrison
Minimum heat-flux widths on outer target follow Eich-scaling for both I- and H-modes
MAST J. Harrison
Eich, et al., NF (2013) &
Brunner (this meeting)
I-modeEDA
H-mode
new C-Mod data
ITER15 MA
Minimum for I-mode heat-flux widths on inner target consistent with Eich-scaling
MAST J. Harrison
C-Modinner target
widthsfor I-mode
• IR thermography of inner target
• q-flux footprint profiles fit to Eich-function
• qparallel inferred from geometry
• mapped to outer midplane, ρ
shot
115
0922
006:
t=0.
745
s
-6 -4 -2 0 2 4 6 8! (mm)
0
100
200
300
400
para
llel h
eatflu
x (MW
/m2 )
"q=1.0 mm- - Eich fit
Significant scatter observed on inner target heat-flux widths
MAST J. Harrison
• Significant scatter also observed on the outer target widths (LaBombard PoP (2011) & Brunner (this meeting))
C-Modinner target
widthsfor I-mode
(~x3 variability)
Search for hidden variables affecting λq is on-going, but as yet unsuccessful
MAST J. Harrison
• Inner target heat-flux widths observed to evolve in time, typically to larger values, but with no change observed for global parameters
• Some scatter in λq due to profile shapes with long fall-offs into PFZ, i.e. when
SEich ~ λq
shot
115
0922
009:
t=1.
298
s
-6 -4 -2 0 2 4 6! (mm)
0
50
100
150
200
para
llel h
eatflu
x (MW
/m2 )
"q=1.34 mm- - Eich fitSEich=
1.24 mm
However, profile-FWHMs still show approx. same variability/scatter
-4 -2 0 2 4 6 8! (mm)
0
100
200
300
400
500
600
para
llel h
eatflu
x (MW
/m2 ) t=0.716-0.724 s
shot
115
0923
025:
S_E
ich(0
.72)
=0.3
7 mm
, S_E
ich(0
.89)
=0.6
8 mm
"q=1.33 mm, SEICH=0.37 mmfit to Eich funct.
fit to Eich funct.
t=0.89 s
"q=2.37 mmSEICH=0.68 mm
For I-mode plasmas Podiv is ~1x to 4x Pidiv
MAST J. Harrison
Inner target q-flux measurements made using IR thermography
Outer target measurements made using TC’s to get Eodiv
tot, then dividing by Δticrf 0 1 2 3 4 5 6Pinput (MW)
0.0
0.2
0.4
0.6
P div
/Pinp
ut
Outer divertorInner divertor
Investigated near-DN I-mode plasmas as way to mitigate inner target heat-flux
• Experiment: modulate SSEP (“δRsep”) in near-DN I-modes
• Pidiv responds to distance to 2nd sepx, while Pidiv
peak does not
0
50
100
150
kJ
WMHD
0
1
2
3
4
MW
PICRF
0.6 0.8 1.0 1.2 1.4seconds
0.00.1
0.2
0.3
0.40.5
MW
Pidiv
0100
200
300
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500
MW m
-2
Idiv Qpara Peak-4-3-2-101
mm SSEP
The movie of the SSEP modulation that was played in the original Power Point version can be found at
http://www-internal.psfc.mit.edu/~terry/Terry_APS_2017_SSEP_modulation.pptx
Summary • Minumum heat-flux widths, λq, on inner target in I-mode are ~1 mm
and are consistent with Eich-scaling, λq~Bpol-1.
• Significant scatter (~x3) in inner target heat-flux widths, but similar to scatter seen for outer target widths. To date, “hidden” variables responsible for scatter have not been found.
• Power-sharing between inner/outer targets for I-mode plasmas is such that Pidiv/Pin ≾ Podiv/Pin by roughly 1x-4x.
• Near-DN operation reduces Pidiv, but doesn’t reduce qidivpeak
significantly until SSEP (“δRsep”) > 0.
• Power handling in I-mode at inner target remains a significant challenge.