overview of east h-mode plasma
DESCRIPTION
2 nd A3 Foresight Workshop on Spherical Torus, January 6 - 8, Tsinghua University, 2013 Beijing, China. Overview of EAST H-mode Plasma. Liang Wang * , J. Li, B.N. Wan, H.Y. Guo , Y. Liang, G.S. Xu , L.Q. Hu for EAST Team & Collaborators . - PowerPoint PPT PresentationTRANSCRIPT
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Overview of EAST H-mode Plasma
Liang Wang*, J. Li, B.N. Wan, H.Y. Guo, Y. Liang, G.S. Xu, L.Q. Hu for EAST Team & Collaborators
Institute of Plasma Physics, Chinese Academy of Sciences
*Email: [email protected]
2nd A3 Foresight Workshop on Spherical Torus, January 6 - 8, Tsinghua University, 2013 Beijing, China
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Outline
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Introduction
H-mode access & power threshold
ELM characteristics, energy loss and divertor power load
Active control of giant ELMs Long pulse H-mode over 30 s in EAST
Summary and conclusion
ASIPPExperimental Advanced Superconducting Tokamak
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Major radius: R0 = 1.9 m
Minus radius: a = 0.5 m
Plasma duration: t=1000 s
Plasma current: Ip = 1 MA
Toroidal field: BT = 3.5 T
Triangularity: δ = 0.3-0.65
SN/DN divertor configuration
Commenced operation on 26 Sept. 2006 First H mode on 7 Nov. 2010H-mode duration over 30s on 28 May 2012Divertor operation over 400s on 21 June 2012
ASIPPEAST Upgrade Capacity & Near-term Plan
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RMP Coils (n=4)
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Outline
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Introduction
H-mode access & power threshold
ELM characteristics, energy loss and divertor power load
Active control of giant ELMs Long pulse H-mode over 30 s in EAST
Summary and conclusion
ASIPPLithium wall conditionings
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• Increasing Li Coverage (85% @2012 vs 30% @2010) • Active Li injection to help operate long pulse H-mode• Need one more oven for full surface coating.
Reduce recycling Suppress impuritiesBenefit ICRF &LHCD couplingMitigate ELMs
ASIPPH-mode threshold power
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Threshold power of EAST H modes is aligned with predictions of the international tokamak scaling 2010 campaign
2012, dithering LH transition
Threshold power shows no dependence on heating method
Appears to have a roll-over ne ~ 2.2 1019/m3
Low density limit for H-mode access
B.N. Wan et al., Nucl. Fusion 53, 104006 (2013)
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Unfavorable BB facilitates H-mode access in EAST
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H-mode access in EAST favors the divertor configuration with ion B× B drift away ∇from the X-point, in contrast to other tokamaks.
Thus, LSN with reversed Bt facilitates access to H-modes Type I ELMy H-mode in EAST was only achieved in LSN.
Reversed Bt, 2010 campaign
Normal Bt, 2012
H.Y. Guo et al., Nucl. Fusion 54, 013002 (2014)
BB ↓
BB ↑
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Outline
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Introduction
H-mode access & power threshold
ELM characteristics, energy loss and divertor power load
Active control of giant ELMs Long pulse H-mode over 30 s in EAST
Summary and conclusion
ASIPPType-I ELMs in EAST
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LSN with LHW+ICRH
Heating power: Pheat~1.5PLH
Good confinement: H98 ~1
Lower density : ne/nG < 0.5
Repetition freq.: fELM < 50 Hz
Peak heat flux: ~10 MWm-2
Contours of js at UI (a), UO (b), LI (c) and LO (d) divertor targets for a typical Type-I ELMy H-mode.
ion sj e
Divertor particle fluxes
L. Wang et al., Nucl. Fusion 53, 073028 (2013)
ASIPPType-I ELM power load, pedestal energy loss
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ELMdiv diaW W
ELMdia diaW W
Pedestal energy loss: ~ 8.5%
Divertor power load: ~ 5%Most of Type I ELM ejected power
is deposited on the outboard divertor
Characteristics of divertor power load and peak heat flux for a Type I ELM.
ELM energy loss and divertor heat load for two groups of coherent type-I ELMs in #41200 & #42556
ASIPPCompound ELMs in EAST
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Characteristic: an initial ELM spike followed by a number of small ELMs.
Achieved in DN (δ=0.46) with LHW+ICRH, Pheat~1.3MW
Good confinement: H98 ~1Density: ne/nG >0.5 ELM frequency: fELM ~50HzThe plasma energy loss & div.
power load: both ~ 4.5% .Peak heat flux : between that of
type-I and type-III ELMs.
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Essential difference between compound ELMs &ELM filaments: different time scale
13Type-III ELM filaments observed by divertor LPs (left) and visible camera w/ BOUT++ (right).
The time scale of a compound ELM: a few msThe interval time betw. adjacent ELM filaments: 150-250μs
X.Q. Xu et al 24th IAEA FEC
ASIPPType-III ELMs in EAST
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The most common ELMs observed in EAST up to now.
Achieved USN, DN, LSN Pheat~PLH: LHW only, ICRF
only, LHW+ICRFfELM=0.2-0.8kHz
ne/nG = 0.2-0.65
Confinement: H98 = 0.5-0.8
No ∆Wdia was observed
∆Wdiv/Wdia : 1-2%.
Peak heat flux: ~2MW/m2.G. S. Xu et al., NF 51, 072001 (2011); L. Wang et al., NF 52, 063024 (2012)
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Three diagnostics (Divertor LPs + IR camera + LFS Reciprocating LPs) independently demonstrated .
L. Wang et al., submitted to Nucl. Fusion, December 2013
Scaling of divertor power footprint width in RF-heated type-III ELMy H-mode
In addition, the systematic experiments of EAST shows the inverse scaling is independent div-configuration (LSN, DN, USN).
ASIPPVery small ELMs in EAST (type-II like)
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Achieved with LHW+ICRH, Pheat~1.7MW, q95 ≥ 4.5
H98= 0.8-0.9, between type-I and type-III ELM regimes
High δ: very small ELMs type-I ELMs when δ was reduced to ~ 0.4.
High density: ne/nG = 0.5 - 0.6
High freq: fELM = 0.8-1.5kHz
Peak heat flux: < 1MWm-2 largely
No ∆Wdia was observed
Broadband MHD mode: 20-50kHzL. Wang et al., Nucl. Fusion 53, 073028 (2013)
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Outline
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Introduction
H-mode access & power threshold
ELM characteristics, energy loss and divertor power load
Active control of giant ELMs Long pulse H-mode over 30 s in EAST
Summary and conclusion
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Demonstrated for the 1st time Edge magnetic topology change by LHCD
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Helical Radiation Belts (helical current sheets) induced by LHCD
Y. Liang, …, L. Wang et al., PRL 110, 235002 (2013)
ASIPPStrong mitigation of ELMs with LHCD
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ICRF-dominated + 10Hz LHW modulation (LHW-off: 50ms ~ ½τE)
H98=0.8; Wdia|LH: 50 100kJ
LHW off: fELM ~150Hz
LHW on: ELMs disappear or sporadically appear w/ fELM~600Hz
Peak particle flux: ↓ by 2-4
Wdia varied slightly: within ±5%
A quick reduction of Гi,div during inter-ELM can be seen when LHW was switched off.
Y. Liang, …, L. Wang et al., PRL 110, 235002 (2013)
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Collaborated with PPPL
Demonstrated for the 1st time ELM Pacing by Innovative Li-granule Injection
Triggering ELMs (~25 Hz) with 0.7 mm Li granules @ ~45 m/s.ELM trigger efficiency after L-H transition: ~100%.Much lower divertor particle/heat loads than intrinsic type-I ELMs.
D. Mansfield et al., Nucl. Fusion 53, 113023 (2013)
ion sj e
Li
ASIPPELM control by SMBI
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SMBI: Supersonic Molecular Beam Injection, Initially developed by SWIP.CN, successfully applied on HL-2A, KSTAR & EAST
X. L. Zou et al., 24th IAEA FEC, San Diego
ASIPPSHF can be actively controlled with SMBI
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Striated Heat Flux (SHF ) region in the far-SOL can be actively controlled with SMBI.
Characteristic of LHCD heating scheme
SMBI significantly enhancing SHF, while reducing peak heat fluxes near strike point.
Achieving similar results with conventional gas puff or Ar seeding.
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SHF can be actively controlled by regulating edge particle fluxes
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For SHF: qSHF ~ ΓiTped, Tped~ 350 eV qSHF
increases with Γi.
At OST: qOST ~ ΓiTdiv, Tdiv ~ Γi-1,
qOST remains similar.
A unique physics feature of ergodized plasma edge by LHCD.
Allowing control of the ratio of qSHF/qOST, thus divertor power deposition area via control of divertor plasma conditions.
J. Li, …, L. Wang et al., Nature Phys. 9, 817 (2013)L. Wang et al., submitted to PSI - 2014, invited talk
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Achieved long pulse H-mode over 30s w/ small ELMs to minimize transient heat load
Predominantly small ELMs with H98 ~ 0.9, between type-I and type-III ELMy H-modes.
Target heat flux is largely below 2 MW/m2.
Accompanied by QCM, continuously removing heat and particles.
J. Li, … , L. Wang et al., Nature Physics 9, 817 (2013)
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Outline
25
Introduction
H-mode access & power threshold
ELM characteristics, energy loss and divertor power load
Active control of giant ELMs Long pulse H-mode over 30 s in EAST
Summary and conclusion
ASIPP Significant progress has been made on H-mode & ELMs toward
long pulse operations in EAST on both technol. & phys. fronts.Various ELM dynamics and their behaviors have been characterized.
LHCD leads to edge plasma ergodization, mitigating ELM transient heat load and broadening the divertor footprint. LHCD + SMBI allows control of SS target heat flux distribution by regulating divertor conditions. H-mode access in EAST favors the divertor configuration with ion B×B drift away from the X-point, in contrast to other tokamaks.Achieved repeatable, long-pulse H-mode over 30 s successfully.
EAST is being upgraded with ITER-like W mono-block divertor and more than 20 MW CW H&CD, offering an exciting opportunity and great challenge for H-mode studies.
Summary & Conclusion
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Thank you!Welcome to join EAST experiments! We will be
right here waiting for you …
EAST – Test Bed for ITER
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Back up
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Mo first wallWater-cooledCryo-pump
LFS & HFS wall: Graphite Molybdenum
2012: Mo + graphite div.
2010: full graphite
ASIPPType-III ELMs in EAST
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The most common ELMs observed in EAST up to now.
Achieved in DN, LSN, USNLHW only, ICRF only,
LHW+ICRH, Pheat~PLH
Frequency: fELM=0.2-0.8kHzDensity: ne/nG = 0.2-0.65Confinement: H98 =0.5-0.8No ∆Wdia was observedDivertor power load: 1-2%.Peak heat flux: ~2MW/m2.
1.25, , ,
1.19 0.08, ,
RF-heated (ITER relevant)
NBI-heated (except C-Mod,
1.3 1.15 ,
(0.63 0 Eich'13. NF08 )) ,
EAST EASTq IR q div LPs p omp
multi machinesq IR p omp
B
B
ASIPPThe very small ELMs are type-II like
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Operation space of Type II ELMs: high δ, high κ, high ne , and high q95
Confinement of Type II ELMs: H98 being 10% less than Type I ELMs Unique feature of Type II ELMs: w/ broadband MHD mode ( 30±10kHz@ASDEX-Upgrade; 10-40kHz@JET)
Time-frequency spectrum of Mirnov magnetic signal.
ASIPPFlexible boundary control with LHCD
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The long pulse H-mode was achieved with dominant LHCD, with additional ICRH.
LHCD induces drives n=1 helical currents at edge, leading to 3D distortion of magnetic topology, similar to RMP
LHCD appears to be effective at controlling ELMs over a broad range q95, in contrast to fixed RMP coils.