26th IAEA FEC 	

Summary : EXC, EXS and PPC 	Y. Kamada, QST	Papers: EXC 101, EXS 57, PPC 26 from 40 devices	
MEDUSA (Costa Rica ): R~0.14m, a~0.1m, GLAST-III (Pakistan): R=0.2m, a=0.1 m........ JET (EU): R~3m, a~1.2m

W7-X, Welcome to EX sessions ! 	

2	

Welcome to EX !	
 Start New Operation	
KTX	
University of Science andTechnology of China
RFP
R=1.4m, a=0.4m
Ip=0.5MA (=>1MA)
Bt max=0.35T (=>0.7T)	

NSTX-U	
Ip~1MA H-modes,
H98 ≥ 1, βN ~4 ≥ n=1 no-wall limit
with weak/no core MHD	SST-1	
Upgraded with PlasmaFacing Components.	

3	

Contents
1. Edge Pedestal System
2. Core Transport
3. Core MHD Stability
4. Operation & Control	* Disruption Mitigation is treatedin the next talk by Dr. D. Hill 	

4	

H-mode Pedestal Structure and Dynamics	
Shafranov Shift	
Fast particles	
Pedestal	

Core	

Plasma Shape (κ, δ, A)	

Height	Δ

Pressure(T, n)	

~	

B field (3D): RMP	
plasma response	
small/no ELM
impurity	
mitigation	
 regimes

ELM 	

minor radius	Width	

Turbulence	

! Flow	

Diffusion	
Pinch	EHO,
WCM, QCM	Stochasticity	Grassy ELM
EDA H-mode
I-modeQH-mode	Heat & Particle
to Divertor 	

grad-p: ELM = Peeling-Ballooning modes (PBMs)
width: small-scale turbulence( KBM...)	
5	

Pressure Gradient ~ Peeling Ballooning Mode 	
COMPASS:The
experimental data
are in agreementwith the EPED
model. (EXP6-35,
Komm)	

Shafranov shift stabilizes
the pedestal gradient, 	

COMPASS	MHD simulations reproduce
experiment very well.
JT-60U and JET: 	
MINERVA-DI: Rotation candestabilize PBMs due tominimizing the 𝜔∗𝑖	
  effect =>better fit to exp. data.
(TH8-1, Aiba)
Multi-machine: JOREK
simulations at low
resistivity/viscosity
reproduce experiment(TH8-2, Pamela)	

JET	

JET and JT-60U:
confirmed in a wide spaceof (κ,δ). Low κ high δ
gives lower grad-p, but
wider	
  pedestal width, thengrassy ELM & good
confinement.
(EX/3-4, Urano )	
	TCV, MAST and
JET :The pedestal
height has beensignificantly
increased by early
increase of βp-core.
(EX3-6, Chapman)	

TCV	

6	

ELM crash new key findings	
KSTAR: Three-stage evolution of ELM
was identified using a 2D imaging: (1)quasi-steady filamentary mode with longlife time n=4-15, (2) abrupt structuraltransformation into filaments withirregular poloidal spacing near the onsetof crash, (3) and multiple filament bursts
during the crash. (EX10-3, Yun)	

Pegasus: J-edge across single
ELMs shows the nonlinear
generation and expulsion ofcurrent-carrying filaments.
(EXP4-51, Bongard)	

7	

Pedestal evolution during the ELM cycle	
JET: Pedestal evolution during the ELM cycle:
not always consistent with EPED (EX3-3, Maggi)
Low D2 Gas:
low-βN: Gradient increases and width constant:
not consistent with KBM constraint

ASDEX-U: 70µs resolution Ti (r)measurement: At ELM, heat flux is
first increased at the separatrix, thenTi(r) becomes flatter. χi comes backsoon to its pre-ELM neoclassicallevel . (EXP6-30, Viezzer) 	

Is J-edge expelledby an ELM crash?	

?	
8	

Pedestal Width: key = ne(r) relative to Te,i (r)	Te	

JET: Pedestal stability improves with
reduced radial shift. JET-ILW tends tohave larger relative shift than JET-C.
(EXP6-13, Giroud)pped	

ASDEX-U: D fueling shifts density profile
outward , and T profile anchored at separatrix=> causes a significant degradation of thepedestal top pressure. (EX3-5, Dunne)ne	
ne,sep(1019m-3)	

pe	
9	L-H Transition Threshold Power 	
JET: Isotope Effect: Nonlinear mass dependence on
L-H power threshold(EX5-2,Hillesheim)	
PD, Nunes)	

DIII-D: Dual Mode Nature ofEdge Turbulence May
Explain Isotope and Density
Scaling of L-H Power
Threshold (EX5-1, Yan)	

Pegasus: Ultralow-A
At low A(~1.2), PLH >> ITPA
scaling by one order ofmagnitude.(OV5-4, Fonck)	
Pegasus	

Threshold Power 	

NSTX	
MAST	

(e)
(a)

(b)
(f)

n

de

e

Io

Electr
on
mode

od

(c)
Ele
Eleccttrronmo e on
mod
de

m

mo

n

Ion

Io

Elec tron
Em
leocd
mod treone(d)

KSTAR: PLH increases with
δB for any cases with n=1,
n=2 or mixed-n. (EXP4-4)	

mod

ne~1.5x10 m
19

-3

e

~1.5x1019mm-3
nne~4.2x10
e
9

-3

19 m
~4.2x10nnee~5x10
m-3

9

-3

ne~5x109m-3

10	

L-H transition: Behavior of turbulence
JET: Radial wavelength of
Stationary Zonal Flows scaleswith the radial correlation
length of turbulence,~ several times smaller
than the width of the edge
radial electric field well.
(EX5-2, Hillesheim)	

DIII-D: The main-ion poloidal
flow acceleration is quantitatively
consistent with Reynolds-stressdriven shear flow amplification(	
  EXP3-11, Schmitz)	

NSTX: The energy exchange between flows andturbulence was analyzed using GPI .The edge fluctuation
do not vary just prior to the H-transition.
=> Turbulence depletion is probably not the mechanism of
the L-H transition in NSTX. (EX5-3, Diallo)
ASDEX-U: L-I Transition: Negligible contributionsof ZFs. (EXP6-29, Putterich)	

11	

ELM-free regimes : extended remarkably	
I-mode	Alcator C-mod :High energy confinement with Temperature pedestal,
L-mode Density pedestal, Small impurity, Stationary
and ELM-free. Extended to full field 8T and current
1.7MA. Confirms weak L-I threshold dep. on B, andwide power range at high B. (EX3-1, Hubbard)	
7.8 T ,1.35 MA	
H98=1
Te0 =7.3keV	
<p>=1.4 atm	QH-mode	
DIII-D: Discovered Stationary
Quiescent H-mode with Zero Net
NBI Torque in double-null shaped
plasmas, characterized byincreased pedestal height & width:sustained for 12τE with excellent
confinement (H98y2 ~ 1.5, 𝛽N ~ 2).	
(EX3-2, Chen)	
decreasededge ExB
shear enables
destabilizationof broadband
turbulence 	

12	

Pedestal fluctuations : variety of interplay	EAST: A new stationary small/no
ELM H-mode was found at low
𝜈𝑒∗ < 0.5, H98 ≳ 1.1, exhibiting a
low-n electro-Magnetic Coherent
Mode. It appears at the low
frequency boundary of TAE gap.
(+ ELM pacing)(EX10-2, Xu)	KSTAR: Broadband
turbulence induced by RMP
damps the ELM amplitude(EXP4-15, Lee)	

HL-2A: EM turbulence was
excited by locallyaccumulated impurities.
Double critical gradients ofimpurity density wereobserved and reproducedby theoretical simulation.	
  (OV4-4, Duan)

HL-2A: Synchronization of GAMs andmagnetic fluctuations was observed in theedge plasmas. (EXP7-27, Yan)	
13	

Remaining Issue:
How is the Pedestal Width determined ?	

Pressure(T, n)	

?

?
When pedestal grad-p is below Peeling-Ballooning limit,
how does the pedestal width evolve and saturate ?
During the ELM cycle?
Controllable?
14	Success of RMP ELM Suppression = Phase and Shape	
DIII-D: ELM control requires
the applied field to couple toan edge stable MHD mode,
directly observed on high fieldside. The response isinversely proportional to ν*.
	  (EX1-2, Paz-Soldan)

KSTAR: Optimal phasing for
n=1 RMP is consistent with
an ideal plasma responsemodeling.(EX1-3, In)	(AUG : EXP6-25, Willensdorfer
MAST: peeling, OV5-3, Kirk )	

ASDEX + DIII-D: ELM
Suppression was obtained
for the first time in AUG at
low ν* with a plasma shape
matched to DIII-D (δ~0.3)
showing the importance ofstable edge kink response.
(PD, Nazikian)

EAST: n=1 RMP, Plasma response
behaves a nonlinear transition frommitigation to suppression of the
ELMs (EXP7-4, Sun) 	

15	

Long Pulse ELM Suppression by RMP: Big Progress 		DIII-D: Fully Noninductive plasmas
with high 𝛽 (≤ 2.8%) and highconfinement (H≤ 1.4) sustained for≤ 2 current relaxation with ECCD
and NBCD, and integrated with
ELM suppression by n=3 RMP; thestrong resonant interaction allows
ELM suppression over a wide
range of q95 (EX4-1, Petty)	
DIII-D	

KSTAR: n=1 RMP ELM suppression was sustained formore than ~90 τE (H89=1.5), and also confirmed to becompatible with rotating RMP, wide q95 (4.75 – 5.25)(EX1-3, In), (PD, Jeon)
EAST: n=1 RMP ELM suppression in long-pulse (> 20s)
was realized with small effect on plasma performance(H98>1) (P7-4, Sun)KSTAR	

EAST	

16	

Core Plasma Transport issues for ITER & DEMO	
Te/Ti ~ 1 ( <= electron heating (α, high energy NB, IC, ECH), high ne) 	
Electron Transport
Small rotation due to small external torque ( => intrinsic torque )Small central fueling ( high energy NB) => density profile ?
Confinement performance with metal divertor can be recovered?
Accumulation of heavy impurity (metal wall) ?
Isotope Effects on Confinement?

17	Thermal Transport at high Te/Ti 	
DIII-D and JT-60U: Positive Shear (PS) shows
reduction in Ti when ECH is added. Negative
Central Shear (NCS) minimizes confinement
degradation even with increasing Te/Ti~1. DIIID shows smaller rise in low-k turbulent
fluctuations in NCS than PS. (EX8-1, Yoshida)
DIII-D / JT-60U(EXP6-14, Mantica)	

χi	
  {High	
  Te/Ti}	
  	
  
χi	
  {Low	
  Te/Ti}	
  	

Te/Ti~1	

JET: High Te/Ti plasmas: Electrontransport evaluated with linear
gyro-kinetic simulations GENE:
most consistent with( ITG/TEM) + ETG.
=> Multi-scale non-linear gyrokinetic simulation underway.

qegB	
Σñ	
  {High	
  Te/Ti}	
  	
  
Σñ	
  {Low	
  Te/Ti}	
  	

DIII-­‐D	

magne1c	
  shear	

Fluctua1on	
PS	
NCS	

R/LTe	
18	Electron thermal Transport 	
NSTX: Electrostatic low-k Gyrokinetic
Simulation (GTS) explains ion thermaltransport , but is not able to explain electrontransport. => high-k ETG / EM is important forelectron transport. Nonlinear GYRO simulation
explains grad-n stabilization of ETG, but notenough => EM? (EXP4-­‐35,	
  Ren)	
electron	

MAST: Fluctuation
measured at the top ofpedestal is consistent
with Electron transport
evaluated with linear
gyro-kinetic simulations
GENE: consistent with
ETG. (OV5-3, Kirk)

W-7X: Te profile shape follows the ECRH
Power deposition-> no indication of profile stiffness(EX4-5, Hirsch)	

MST: Drift wave turbulence(TEM) emerges in RFP
plasmas when global
tearing instability is
reduced by PPCD.
(EXP5-17, Brower)	
19	

Density Profile => low ν* ITER ? 	
JET: Density peaks withdecreasing υ* => experimentally
determined particle transportcoefficients. =>suggest that NBI
fueling is the main contributor tothe observed density peaking.
(EXP6-12, Tala)	

DIII-D: The density scale length R/Ln
is well-correlated with the frequencyof the dominant unstable mode, withthe peaking when the turbulenceswitches from ITG to TEM.
(EXP3-9, Mordijck)	

R/Lne	

FTU: The density profile
evolution in high density regime
has been well reproduced using
a particle pinch term withdependence on temperature
gradients (U= DT /Te ∂Te/∂r)(EXP8-24, Tudisco)	
ν*	

DIII-D: Change in peaking is
reproduced by changes in corefueling only . (EXP3-9, Mordijck)	
  

ISTTOK:Edge electrode biasing improves particle
confinement by reducing radial transport via ExB shear
layer formation. (EXP7-36, Malaquias )	
20	

Confinement towards ITER: high βN is the key		
AUG, C-Mod, DIII-D, JET and JT-60U: 	
Stationary H-mode discharges at q95=2.7-3.3:
1) The maximum H98 increases
at lower ν*.
H98y2	
2) H98 increases with βN,
however for metal wall H98
significantly reduced (~0.8-0.9)
at βN≤1.8, H98~1 is obtained
only for βN~2 or higher.
(EX6-42, Sips)
	
  
βN	
	
  
H98y2		CFC	JET-ILW: stationary (5s)
ITER Baseline Operation
at high-δ (~0.4) achieved
at 2MA/2.2T, q95=3.2.
New high-δ configuration
optimized for pumping
H=1-1.1, βN=1.8-2.1 but
n/nGW~ 0.5 	
  (EX/P6-11, De la Luna)

Metal	βN	21	

Avoidance of Heavy Impurity Accumulation ~ good
T-10: W / ECH
After ECRH start a fast
decay of core radiation
occurs. (EXP8-36,
Nurgaliev) 	

ASDEX-U: Central ECH and ICRH to
NB heated H-mode shows the impactof Qe/Qi on the impurity turbulent
diffusion as predicted by Nonlinear
gyrokinetic simulations with GKW(THP2-6, Angioni) 	

JET	

ITER Prediction: No
strong W accumulation
expected in ITER Q = 10
plasmas due to low NBI
fueling. W accumulation in
H-L transitions can takeplace, optimization ofheating and fueling rampdown required. (PPC2-1,
Loarte)ASDEX-U 	KSTAR: Ar / ECH( EXP4-18, Hong)	
HL-2A:Al / ECH
m/n=1/1(EXP7-21, Cui)

JET: W/ ICRF minority
Central ICRH is beneficial on tungsten
transport in the ITERbaseline scenario(EXP6-16, Goniche )Alcator C-mod: W / ICRF minority (EXP3-3,	
  Reinke )	
22	

Impurity Transport in the helical system:
rotation shear & turbulence drive	
LHD: Carbon density profile peaks
with decreasing Mach number ~rotation gradient (EXP8-4, Nakamura). 	

TJ-II: Dual HIBP: ECRH enhances
turbulence and amplitude of Long-RangeCorrelations (LRC) for potential.
(EXP7-44, Hidargo)	

23	

Intrinsic Torque & NTV 	DIII-D + JET : The
total intrinsic torquein the plasma is
1.0
found to increase atlower ρ* (=favorable
way to ITER).
0.1
0.001
(EX11-1 Grierson
EXP3-13 Degrassie)	
DIII-D : Simulations
with GTS gyrokinetic code
reproduces
reversal of core
intrinsic rotation(EX11-1 Grierson)	

Norm. Intrinsic
TorqueITER

DIII-D
JET

ρ*

0.010

Alcator C-mod:	
  Directionof core rotation changes
in the following LHRF
injection depends on thewhether q0 is below or
above unity.
(EXP3-2,Rice) 	
KSTAR+NSTX: Neoclassical Toroidal
Viscosity (NTV) Torque: The measured
rotation profile change due to the 3D
field (EXP4-33, Sabbagh) 	

24	

Confinement: Isotope Effects / Mass Dependence	
Heliotron-J: The turbulence scale size
increases as D2 gas becomes dominant. = The
first evidence for the isotope effect on
turbulence-zonal flow system in helicalsystems. (EXP8-20: Ohshima)	

RFX-mod: 3D RFP Confinement isbetter for D than H (OVP-2, Zuin)

25	

Improved Confinement Performance: ITB	DIII-D: Large radius ITB and excellent
confinement due to Shafranov Shift
Stabilization. (EX4-2, Qian)	

HL-2A: Ion ITB
was observed at
the q=1 surface.
ITG is suppressedby the toroidal
rotation shear.
(EX8-2, Yu)
	

LHD: High Ti & Te > 6 keV were
simultaneously achieved by highpower ECH injected into NB heatedplasmas characterized bysimultaneous formation of electron
and ion ITBs. (PPC1-1, Takahashi).	

26	

Transport hysteresis & non-localness	
Multiple Machine: Transport
hysteresis in core plasmas is
widely observed.	

Modulation ECH: Difference between results from theinward pulse and the outward pulse becomes larger as
the harmonic number increases ( EXP8-15, Kobayashi)	

The core hysteresis involves twoelements:
1. Interaction at long distance
2. Direct influence of heating ontransport/fluctuations=>‘The heating heats turbulence’(OVP-8, Itoh)	

harmonic number of modulation	
KSTAR: The non local transport (NLT) can beaffected by ECH, and the intrinsic rotation direction
follows the changes of NLT. (EXP4-17, Shi)	

27	

Effects of 3D field on equilibrium & stability	
DIII-D & RFX-mod : Role of MHD dynamo in
the formation of 3D equilibria.
high-β tokamak :The MHD dynamo model
predicts current redistribution consistent with
DIII-D experiments(EX1-1, Piovesan )	
DIII-D (core)	

LHD: Phase shifted magnetic islands
from externally imposed m/n = 1/1 RMP
was obserbed (EXP8-8, Narushima)	
J-TEXT: RMP increases the density limit
from less than 0.7nG to 0.85nG andlowers the limit of the edge safety factor
from 2.15 to 2.0. (OVP-6, Zhuang)	
EXTRAP T2R: The resonant MP produces
tearing mode braking and locking consistent
with the prediction. (EXP5-18, Frassinetti )	

28	

Sawtooth, high β stability	
KSTAR: validated q0>1 aftersawtooth crash: tearing mode
evolve (e.g. 3/3 to 2/2, 1/1)	
(EXP4-3, Park, EXP4-27, Ko)	LHD: Central β of thesuper dense core plasma
is limited by "core density
collapse" (CDC). A new
type of ballooning mode
destabilized from the 3D
nature is the cause of the
CDC. (EXP8-10, Ohdachi)	

RELAX: The discharge duration is limited(RWM). The
central βp~15% was achived in the Quasi-Single
Helicity (QSH) state.(EXP5-22, Masamune)	

29	

Disruption Prediction/Characterization	
Alcator C-mod & EAST: Developing Disruption
Warning Algorithms Using Large Databases.
(EXP3-8, Granetz)	
NSTX: Disruption Event Characterization and
Forecasting (DECAF) code has the potential to
track RWM stability in real-time for disruption
avoidance. (Berkery, EX/P4-34 ) 	
ADITYA: The current quench time is inversely
proportional to q-edge. (Tanna, OV/4-3Rb)	

30	

Expanded High β Regimes 	
KSTAR: High βN, up to 4.3
LHD: High-β ~ 4% was
was achieved with high ratios
produced by multi-pelletof βN/li up to 6.3.	
  High βN ~injections at low ν*.
3.3 was sustained for 3 s,
Improved particle
confinement was observed and was limited by a 2/1
during a high-beta discharge tearing mode.
(EXP4-2, Park)	
produced by gas-puff.
(EX4-4, Sakakibara)	

PEGASUS: With Local
Helicity Injection (LHI),
βt~100% was achieved, often
terminated by disruption(n=1)(OV5-4, Fonck)	

31	

Operation: Plasma Current Rump-up " ITER & DEMO	
MAST: In Ip ramp-up, the realcurrent diffusion is slower
than TRANSP. But, it is wellmodeled during Ip flat top.
(OV5-3, Kirk)

DIII-D: There are strong
interactions between Te,
fluctuation, thermal transport,
safety factor, and low-orderrational surfaces.
(EXP3-10, McKee)	

JA-DEMO: Reduction of
CS flux consumption at Ip
ramp-up(EX/P8-38, Wakatsuki)

By optimization of both Te
and q profiles, ~20%
reduction of flux
consumption is possible.

Improved modelingis needed for DEMO design	=> CS size
= economy of DEMO		32	

Control of ITER & SC tokamak operation 	For ITER Plasms Control system (PCS)
KSTAR: Extending verticalstabilization
Fusion and Plasma Application Laboratory
1
Seoul National University• Preliminary design of the ITER PCS
controllability (EXP4-12, Hahn)¾ Successful start-up with ITER-level E , less than 0.3 V/mfocusing on the needs for 1st and early ¾ TPC field structure made by ITER geometry, by using PF#1 and #6¾ Validation of TPC withidentical ECH/ECCD
condition of ITER Particle
KSTAR:
Trappedplasmas. (EXP6-36, Snipes)
 Implementation of the TPC start-up scheme to ITER based on KSTAR results
Configurationfor
EC and “reduced E ”¾ Widen operation range
in terms of D prefill, poloidal
field strength,¾ Early, low V , and fast I initiation with ~10 m pre-ionization plasmas
plasma breakdown• Control analysis and design tools¾ 600 kW / 170 GHz 2 harmonic, toroidal field 2.7 T Efficient
using TPC than Lee)
field null
(EXP4-14,
developed at DIII-D have been appliedin ECH-assisted startup
studies supporting the ITER PCS design.
7(EXP6-37, Humphreys) 100 Toroidal angularL
125 for JT-60SA
TCV: EC wall conditioning
t

2

loop

t

p

18

-3

max
q

5

max

Lq<LqRe Current (kA)

optimal setpoint

100

3
2

D115
	
  removed
2

BV+BR	
  

0.6
0.5

He	
  pumped
110 pressure
Total	
  0.3
in KSTAR 0
EX/P4-14100
ECH-assisted
trapped particle configuration−1 plasma start-up
0.2
Busing	
  only	
  

0
50

4

0.4M.G. Yoo, Y.S. Na and Y.S. Hwang 105
1 J.start
J. Lee,Kim, Y.H. An,(SNU, NFRI)Im Current (kA)

5

0

120

end

5
0
10

(EXP8-31, Douai)
atoms/molecules	
  (Pa.m 3)

0

6

Im Current (kA−t)

Real-time Error
Field Correction:
Varies correction
field amplitude
phase to maximize
plasma rotation

momentum
50 Lq (kg m2/s)

Toroidal angular momentum (kg m2/s)

nd

150

200

Simulation Time (s)• Generation of the disruption mitigation.
(EXP6-38, Pautasso)
	

250

300

−2
−2

0

V

0.1

2

4

Re Current (kA−t)

0

0

2

6

95

4
6
8
10
number	  of	
  shots

12

14

33	

• State estimation merging multiple
diagnostics.
• Model-based plasma controllers

EC powers [MW]advanced algorithms in PCS

Advanced control 	• Real-time actuator management

actuator
control
actuator
control
actuator
controlsystems
systems
systems1

TCV#54534

P Supervision
A

PB

0.5
Actuator0
manage-Plasmaforecasting& off-normal
event
detection

PlasmaState
Reconstuction

ment

controlled with
DIII-D : Physics-model-based q-profile• Predictive controller of plasma beta tested on
two gyrotrons toFeedback Control (EXP3-23,
Schuster)TCV (figureright)
follow Ref.

• Numerical optimization of plasma evolution
KSTAR: Physics-Based during
Profileramp-up
Controland ramp-down

A
B

00
2

×10 190.3
1
Estimate
Estimate
Ref.
Ref.

0.2
0
4

0

0.5

1

1.5

2

time [s]Gas cmd• Real-time state reconstruction based on realmodel-based andtime RAPTOR code + RT-diagnostics

β (%)
[MW]
<n e t> V [m -3 ] EC powers
Gas cmd

β t (%)

TCV, ASDEX-U & ITER:
Real-timemodel
DIII-D :demonstrated • Plasma supervision
Controllers
0.3
Controllers
Controllers
plasmaAdaptive Real-Time • Model-based event prediction -based[Real-time
control] state estimation
Estimate
0.2
Ref.
(EX/P8-33, Felici)
Pedestal Control with
TCV#54534
41• These are being developed	 and tested
RMP by real timePP
on TCV and AUG in view of theirstability evaluation2
0.5
TCV: Beta is(EXP3-21,Kolemen) application in ITER, examples:
estimated by

2(EX/P4-13, Kim)F. Felici et al. - IAEA 2016 Kyoto, Summary slide. EX/P8-33 STOR-M: Toroidal Flowwas modified
through Momentum 0Injection
by CT Injection
×10
2
Realtime tokamak simulation with a first(EXP7-39, Xiao )principle-based neural network turbulent
1	
Estimatetransport model (EX/P6-45, Citrin)
Ref.
FT-2: Improved Core
Confinement
0
0
0.5
1
1.5
2
Observed with LHCD (EXP7-41,
time [s]Lashku)	
NSTX-U: Feedback Control Using
TRANSP for Non-inductive Scenarios(EX/P4-43, Boyer)34	<n e > V [m -3 ]19

Steady-state Advanced Tokamak Operation Extended	
ASDEX-U: Fully non-inductive
operation with W wall at Ip= 0.8
MA( 40% NBCD, 50 % boostrap,
10 % ECCD). ECCD is used to
tailor current profile for optimum
stability and qmin > 1.5(PD, Stober)

KSTAR: Fully non-inductive
current drive with fBS < 0.5,
βp > 3, βN ~ 2, H89 ~ 2.0
with NBCD & ECCD
(Ip=0.45MA) (EXP4-1, Yoon)	

EAST: 60sec H-mode
Demonstration of full-CD (LHCD, ECCD,ICRRF) with W wall, βP~1.1; q95~6.3, t/τR~15,
H98>1.1.(EX4-3, Garofalo)35	

New Tokamak World Record of
volume averaged pressure 2.05atm
was achieved in Alcator C-mod 	

36	Summary: EXC, EXS and PPC 	
'3D' has become more common language and tool.	
Understanding of H-mode & ELMs, and practical control scenarios
have been progressed toward ITER.
( such as, wide applicability & steady-state ELM mitigation by
RMP, understanding of confinement with W-divertor )Transport / turbulence / instabilities are reproduced well bysimulations	

ITER

Encouragements towards next FEC	
Width of the H-mode pedestal
Electron Transport / multiple scale transport
Disruption Prediction
Enhanced Effort towards SS tokamak operation
37