18th iaea fec
DESCRIPTION
18th IAEA FEC. 聚变研究朝着反应堆要求的方向发展,即要在准稳态下同时实现: 高约束 H 、高 N 、高 f BS 、 完全非感应电流驱动、有效的加热和排灰等。 ITER 物理和工程基础的积累。 有效的外部控制。( ITB, NTM, RWM, N …) 物理研究进展。. 重要结果 (JT-60U). 在 RS 和 ELMy H 模下实现准稳态的完全非感应电流驱动( high P ; HH Y2 ~1.4; N ~2.5 with N-NB, RS; HH Y2 ~2.2; N ~2 with f BS ~80%) - PowerPoint PPT PresentationTRANSCRIPT
18th IAEA FEC
• 聚变研究朝着反应堆要求的方向发展,即要在准稳态下同时实现:
• 高约束 H、高 N、高 fBS、完全非感应电流驱动、有效的加热和排灰等。
• ITER物理和工程基础的积累。• 有效的外部控制。 (ITB, NTM, RWM, N…)
• 物理研究进展。
重要结果 (JT-60U)• 在 RS和 ELMy H模下实现准稳态的完全非感应电流驱动 (high P; HHY2~1.4; N~2.5 with N-NB, RS; HHY2~2.2; N~2 with fBS~80%)
• RS: QDTeq=0.5 for 0.5s
• NTM suppression by ECCD, enhanced N by with wall stablization.
• ITB control by toroidal rotation profile modification • RI mode by Ar gas puffing.• Current drive efficient 1.551019A/m2/W by N-NB He
*/ E~6 by both leg divertor pumping (increasing 40%).
重要结果( JET)• In support of the ITER physics basis.
• Positive enlongation and current scaling in the ITER scaling law IPB98(y,2).
=0.0562P-0.69B0.15I0.93a0.78n0.41a0.58R1.39M0.19
He*/ E~6 (15), 0.5<(He)<1.0 (0.2) No problem for helium tran
sport and exhaust (in ELMy H mode).
• HFS pellet: n/nG=1.6 with H97=0.5; n/nG=0.85 with H97=0.9
• NTM: Ncrit~3.3% at q95~3(3.3), stablization, destablization, low * raising threshold.
• Advanced Scenarios:(MHD,Fuelling, Steady-state, limit…)
重要结果 (DIII-D) NH89P~9 for duration/ E ~ 16 (2s) (fBS>50%, fnon-ind>75%,
q(0)>1.5, N~4li, RWM, NTM,)
NH89P~7 for duration/ E ~ 35 R/ E > 3 (hardware limitation, divertor2000, q(0)~1, NTM, ECCD)
• QDB, ion, electron TB in the core and edge, non ELMy edge (ne, impurity control, high , new divertor-2000).
• Active control RWM, , NTMs stablization by ECCD
• ne/nGW~1.4 by maintaining pedge.
• 36 channel MSE
重要结果( ASDEX-U)• Enhanced ELMy H-mode at nGW (H~1, type II ELMs, ne pe
aking, ion and electron T profile stiffness). N=2.6, HH98P=1.7 (H mode, ne peaking, stationary, flat mag
netic shear qmin~1).
• Ion and electron ITB with up to 16 keV (Te~Ti~10keV, N=1.8, HH98P=1.5).
• Fully current drive (BS60%+NBCD, N=2.7, ne~nGW; ion ITB with H-mode edge; co-ECCD (>80)).
• NTM suppression by ECCD.• First wall / targets: no influence on plasma behavior.
重要结果• Alcator C-mod: the core rotation is strongly influenced by the c
ore density profile not just by effects in the H-mode barrier; Future program: LHCD off-axis CD 1MA with fBS~70% in steady-state advanced tokamak operation.
• Tore Supra: Ergodic Divertor, 30s discharge, 20s flat top at BT~3T, IP~1.4MA, PLH~3.7MW ne~1.61019m-3, 1Hz, 20kA modulation, gas puffing in divertor; Two limitation: divertor coil cooling < 30s, LH at high power ~30s.
• Triam-1M:HIT mode, ECD mode, Bi-directional current drive, Wall equilibrium (repeated saturation, refreshing, low-E neutrals cause co-deposition of Mo)
Overview on Chinese Tokamak Experimental Progress
HT-7 team, presented by J.K.XieInstitute of Plasma Physics, Chinese Academy of Sciences, Hefei, China
HL-1M team presented by Y. LiuSouthwestern Institute of Physics, Chengdu, China
KT-5 Team presented by Y.Z. WenUniversity of Sciences and Technology of China, Hefei, China
CT-6B Team Presented by L. WangInstitute of Physics, Chinese Academy of Sciences, Beijing, China
I. Introduction (Tokamaks in China)
• HT-7 Super-conducting Tokamak in ASIPP high performance plasma under steady-state• HT-6M Tokamak in ASIPP heating and edge plasma physics• HL-1M Tokamak in SWIP heating and advanced fueling• KT-5 Tokamak in USTC edge turbulence/transport • CT-6B in IP/CASalternative concept development
2. HT-7 Tokamak Experiments
2.1 Outline
2.2 LHCD experiments
2.3 ICRF heating
2.4 ICRF conditioning
2.5 Pellet and supersonic beam injection
2.6 ICRF Assistant Start-up
2.7 Summary
ASIPPASIPPHT-7HT-7
HT-7 Superconducting TokamakHT-7 Superconducting Tokamak
R = 1.22m
a = 0.275m (Mo Limiter)
Ip = 100~250 kA (250)
ne = 1~8x1013cm-3 (6.5)
BT = 1~2.5T(2.5)
Te = 1~2 KeV (1.5)
Ti = 0.2~0.6K eV (0.8)
t = 1~ 5s ( 10.7s)
ICRF: f = 15~45MHz,
P = 0.3MW, CW(0.3, 1.5s)
LHCD: f = 2.45GHz,
P = 1.2MW, 10s (1 MW, 5 s)
Pellet injector:
up to 8 pellets /per shot
Supersonic beam injection: <1.0 km/s
Pump limiter ( Mo head)
Main Goal: Steady-state advanced operation and related physics
( Ip > 100kA, Ne>1.0x13cm-3, t=3~10s)
ASIPPASIPP HT-7HT-7
LHCD Experiments (1)
• Long pulse discharge sustained by LHCD for > 6 s
• Full current drive for > 3 s
• Transformer is recharged by LHCD
0 1 2 3 4 5 6 70.00.51.01.5
Ha
time (sec)
0
1
2
VS
3.6
3.7
#33132
PLH
=250kWPL
H
0.0
0.5
Ne(
1013
/cm
3 )
0
2
4
Vp
(V)
020406080
Ip(k
A)
HT-7HT-7ASIPPASIPP
LHCD Experiments (2)
• High performance ( Ip = 100 kA, ne 11013 cm-3, Te > 1 keV discharges sustained by LHCD for > 3 s
see X. Gao EXP4/12 Monday 9 Oct.
• Quasi steady state H-mode like plasmas with density close to Greenwald limit was obtained by LHCD
see J. Li EXP4/11 Monday 9 Oct.
0 1 2 3 40.00.51.01.52.0
I EC
E
Time [sec]
0.5
1.0
1.5
Te by TSTe(
0)[k
eV]
3.6
3.7
#31586
P_LHW
=250kW
PL
H
0.0
0.5
1.0
1013
/cm3N
e
0
2
4
Vp
(V) 0
50
100
IP(k
A)
HT-7HT-7ASIPPASIPP
LHCD Experiments (3)
0.0 0.4 0.8 1.2 1.60
100200300400
LHCDPL
H[k
W]
Time [sec]
0
40
80
Ip [
kA]
Ip
0
2
4
VP [
V ] Vp
0.0
0.5
1.0
1.5N
e[10
19m
-3]
Ne
• Plasma current ramp-up by LHCD achieved IP=74kA at PLH=320kW/900
• Global LHCD efficiency
.
219.exp
)))45.1][(8.4exp(085.01(5.0
]/10[
theorCDT
LH
pCDeCD
TB
WAmP
RIn
HT-7HT-7ASIPPASIPP
ICRF Antenna ICRF Antenna ConfigurationsConfigurations
ASIPPASIPP HT-7HT-7
IBW Heating• F=24-30MHz, t = 0.2-1.5s,
• P = 40-150kW
• Te heating, - 100-500eV
• Ti heating 100-300eV
• Ne increased and Ne(r) peaked
• Wj increased. E, p increased
• ITB was observed
50 100 150 200 250 300 350 400 450
0.5
0.6
0.7
0.8
0.9
1.0
1.1
IBW 50kW
Te (
Kev
)
t (ms)
-1.0 -0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 1.00.0
0.5
1.0
1.5
2.0
2.5
3.0
3.5
4.0
ITB
OH100ms IBW180ms IBW290ms OH350ms OH400ms
S-X
inte
nsity
(a.
b un
it)
r/a
ITB were clearly shown at the r/a = 0.6. The H was observed at r/a =0.27 and the caculation showed at 0.31 which is about 1.1cm
ASIPPASIPP HT-7HT-7
See Y. Zhao EXP4/30 Monday 9 Oct.
IBW Experiment
•Particle confinement
improved
•Fluctuation suppressed
•Coherence decreased
•k shifted towards to
negative, electron drift
direction
•IBW produced poloidal flow in e-drift direction in the SOL
see B.N. Wan EXP5/11 Tuesday 9 Oct.
-9 -6 -3 0 3 6 90.0
0.5
1.0(d)
s(k
) /a
.u.
k/cm-1
0 40 80 120 160 200-8-4048 (c)
k (f
) /c
m-1
f/KHz
0 40 80 120 160 2000.0
0.5
1.0(b)
C(f
)
0 40 80 120 160 200
1E-30.010.1
1
(a)
S(f
)/a.
u. before IBW
during IBW
HT-7HT-7ASIPPASIPP
ICRF Boronization (1)
0 4 8 12 16 20 24 28 320
2
4
6
8
Par
tial
Pre
ssure
(x10
-6)
e/m
Before Boronization After Boronization
Comparing for the QMS before and after RF boronization
The residential gas analysis during ICRF boronization.BT = 1.8T, PRF = 10 KW, f = 30 MHz
ICRF also for Cleaning, BoronizationSiliconization, Isotope control, etc
Leads to:*Reduced impurity influxes and radiation power*Improved energy/particle confinement times *Extended operation limit
HT-7HT-7ASIPPASIPP
ASIPPASIPP
The boron film property for the fresh film and the film after 250 shot. The film depth is about 350nm and can last 1500~2000 shots
The Hugill diagram was extended after ICRH boronization and Siliconization
ICRF Wall Conditioning
HT-7HT-7
Pellet Injection with IBW heating
-10 -5 0 5 10 15 200.0
0.5
1.0
1.5
2.0
n e.Te (
x10
19 k
eV/m
3 )
Minor Radius (cm)
2ms before PI 3ms after PI 40ms after PI
0
1
2
0.0
0.5
1.0
2ms before PI 2ms after PI
-20 -10 0 10 200
1
2
Te(r) (keV)
__
ne (x10
19 m
-3)
Minor Radius (cm)
-10 0 10 20 300.0
0.5
1.0
3ms after PI 40ms after PI 100ms after PI
Minor Radius (cm)
• PI has favorable impact on off-axis RF heating• PI improve the coupling of RF wave • PI improve confinement • PI can influence profile and local transport
see Y. Yang EXP5/12 Tuesday 9 Oct.Te and ne with IBW after PI
Pe profile with IBW Te profile without IBW
HT-7HT-7ASIPPASIPP
ICRF assistant startupASIPPASIPP
HT-7HT-7
ICRF 130 kW EOH~2.5V/m ERF~0.9V/msee J.R. Luo EXP1/01 Thursday 5 Oct.
ICRF assistant startup favor to
full super-conducting tokamak
HL-1M ExperimentSWIPSWIP
HL-1MHL-1M
Outline of HL-1M experiment R = 1.02 m, a = 0.26m, BT = 3 T in circular limiter configuration. Objectives: high power auxiliary heating (NBI, ECRH, ICRH),
LHCD, new fueling techniques PI, supersonic molecular beaminjection (SMBI).
Wall conditioning: Boronization, Siliconization and lithiumization. The maximum parameters achieved in ohmic heated plasmas:
IP=320kA, ne=8×1019m-3, Bt=2.8T. ICRF 0.3 MW, NBI 0.4 MW, ECRH 0.25 MW, LHCD 1 MW Improve the energy confinement and density limit by PI and
SMBI. Reversed magnetic share produced by off-axis ECRH and LHCD.
Off Axis ECRH ExperimentsSWIPSWIP
HL-1MHL-1M
• 75GHz /300kW(o-mode)
• IP=150-200kA, Bt=2.4-2.7T
• ne=0.5-4.0×1013cm-3.
• Te increased 450eV -> 700eV
When rres ~ rq=1
• The MHD activities were modified
• The double ST means that the reversed magnetic shear is formed
see E. Wang EXP5/08 Tue. 9 Oct.
PI Experiments
SWIPSWIPHL-1MHL-1M
• Size: 2×φ1.0, 3×φ1.2, 3×φ1.3mm
• up to 8 pellets injected• improved energy and
particle confinement• enhanced density limit• asymmetric cloud in
toroidal and poloidal direction
(c) Toroidal (solid line) and poloidal (dashed line) emission profile
(a) pellet ablation cloud
(b) Contour line of the intensity of ablation cloud
0.0 12.2(cm)5.6
FIG. 2 Asymmetry in the intensity of pellet cloud
pellet dir.↑
PI Experiments (2)SWIPSWIP
HL-1MHL-1M
• Ablation and penetration are investigated by fast CCD
• q-profile was estimated with the inclination angle of ablation cloud with respect to the torus
115.5mm
0.32ms
r/ a
The evolution of radial profile of the Hα emission during pellet injection. (b) The contour for (a)
(a) (b)
SMBISWIPSWIP
HL-1MHL-1M
•High fueling efficient and deep penetration.
•The hydrogen cluster-like may be produced in the SMB, which is beneficial to deep injection.
See L.H. Yao EXP4/13 Mon. 9 Oct.
Zone of silence M>>1
Po,ToM<<1
Nozzle,M=1
Mach disk shock
HL-1MPlasma
120 200 280 360 440
t (ms)
1.2
0
358
-77290
110
100
10
1.67
0
HC
N(1
013c
m-3)
OF
9(a.
u.)
OF1
1(a.
u.)
Te-
g(eV
)n e(
1012
cm-
3 )
Edge Plasma Parameters during SMBI HCN_average electron density, OF9, 11_Edge Hsignals far from injection port 22.5o, and 135o, Te-g & ne _Plasma temp
erature and density at r = 23 cm
Density limitSWIPSWIP
HL-1MHL-1M
•Ip~100 kA, ne > nGreenwald
•Ip~200 kA, ne ~ 80% nGreenwald
•Boronization, siliconization, lithiumization is used
ne (101
9 m-3)
t (m
s)
ne<8.2x1019 m-3 ; dne/dt<3x1020 m-3s-1
Prad/Pin>60% before minor disruption
Disruption occurs after MHD instability in 6ms
0
5
10
15
0 5 10 15
MBI(H)
GP(D)
GP(H)
Pel l et
MBI (H+D)
Green
wald l
imit
IP/a2 (10-1MAm-2)
n e(10
19m
-3)
FIG. 4 The density limit versus IP for gas puffing(GP) molecular beam injection and pellet injection
USTCUSTCKT-5KT-5
Experiments in KT-5 Tokamak
Observation of spatial intermittency
• A sharp variation, refered to spatial intermittency, at some radial position superimposed on a slow change the fluctuation.
• Such structure help to understand the local shear build-up to for the H or H-like mode transition.
• Profiles of (a)the density and potential fluctuations, (b)particle and energy transport fluxes, (c)correlation length , (d) bicoherent coefficients of the density and potential fluctuations. (Ip=10kA, BT=0.38T, qa=5.3,ne=1.39x1019
m-3)
USTCUSTCKT-5KT-5
Er by biasing
• The turbulence suppressed with the change of Er induced by the biasing
• The poloidal flow contributes to the main part of the Er,
• The change of the poloidal flow has a lead of about 20s to the formation of Er, suggesting that a radial current drives a poloidal flow, in turn drives the radial electric field.
IP/CASIP/CASCT-6BCT-6B
Experiment in CT-6B TokamakAC Operation• The poloidal magnetic field in the plasma
measured by internal magnetic probes
• The plasma current profile and flux surface reconstructed.
• When the first positive current pulse drops, a negative current component appears on the weak field side.
• When the total plasma current passes through zero, two current components flowing in opposite direction coexist.
• The existence of flux surface and rotation transform provide the particle confinement during the current reversal
IP/CASIP/CASCT-6BCT-6B
Experiment in CT-6B Tokamak
ECW StartupA discharge between a pair of electrodes is introduced and form a magnified toroidal current in a strong toroidal field and a weak vertical field, in which the electron cyclotron wave produces a background plasma
Fluctuation of H is analyzed by waveletcorrelation. Coherent structures areidentified in radius-time plane with of20-100 s and r 1-2 cm in V shearregion. Bicoherence analyses showsstrong coupling between high- (>50 kHz)and low- frequencies (~35kHz) in thecoherent structure region. The parallelflow instability is identified and its effectson tranport is studied.
Fluctuation study