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