status of the advanced research under long-pulse operation in … · 2015-05-27 · status of the...

Status of the advanced research

under long-pulse operation in KSTAR Yeong-Kook Oha, J.G. Kwaka, K.R. Parka, Y.S. Baea, S.W. Yoona, Y.M. Jeona, Y. Ina,

J.M. Kwona, S.H. Honga, Y.U. Nama, Y. Chua, S.G. Leea, B.H. Parka, J. Honga, H.S. Ahna,

J.H. Choia, J.D. Konga, S.T. Kima, H.L. Yanga, H.K. Kima, D.S. Park a, H. Parkab,

W.H. Choec, Y.S. Nad, G.S. Yune, Y. Parkf, S. Sabbaghf, and KSTAR team

a National Fusion Research Institute, Daejeon, Korea

b Ulsan National Institute of Science and Technology, Ulsan, Korea c Korea Advanced Institute of Science and Technology, Daejeon, Korea

d Seoul National University, Seoul, Korea e Pohang University of Science and Technology, Pohang, Korea

f Princeton Plasma Physics Laboratory, Princeton, NJ, USA

8th IAEA TM Steady State Operation of Magnetic Fusion Devices, May 26-29, 2015, Nara, Japan

- 2 - 8th IAEA TMSSO – Yeong-Kook Oh (May 2015)

OUTLINE

Introduction

Mission and machine status

Highlights of the recent experiments to the steady-state operation

Long-pulse extension toward the steady-state operation

High beta operation above the no-wall limit

Development of the advanced operational modes

Validation of the low error field

ELM control using in-vessel control coils

Advanced research utilizing unique features of KSTAR

Advanced plasma control

Understanding the error fields effects with the 3D fields

Improved heating & current drive

Plasma wall interaction

Diagnostics & Modeling

Summary


OUTLINE

Introduction














Summary


KSTAR mission and achieved key parameters

Parameters Designed Achieved

(~2014)

Major radius, R0

Minor radius, a

Elongation,

Triangularity,

Plasma shape

Plasma current, IP

Toroidal field, B0

H-mode duration

N

Superconductor

Heating /CD

PFC

1.8 m

0.5 m

2.0

0.8

DN, SN

2.0 MA

3.5 T

300 s

5.0

Nb3Sn, NbTi

~ 28 MW

C, CFC, W

1.8 m

0.5 m

1.8

0.8

DN, SN

1.0 MA

3.5 T

45 s

4.0

Nb3Sn, NbTi

~ 7 MW

C

Achieved key parameters KSTAR missions

• To achieve the superconducting

tokamak construction and operation

experiences

• To explore the physics and

technologies of high performance

steady-state operation that are

essential for ITER and fusion reactor


KSTAR machine status in 2015 campaign

NBI-1

5.5 MW / 50s)

170 GHz ECH

(1 MW / 50 s)

110 GHz ECH

(0.7 MW / 2 s)

30~60 MHz ICRF

(1 MW / 10 s)

5 GHz LHCD

(0.5 MW / 2 s)

XICS

FIR

ECEI

MIR

H

ECE

Thomson

Bolometer

CES / BES

MSE

SXR / IR /

Deposition

mmWI

Reflect.

105/140 GHz ECH

(1 MW / CW)


OUTLINE

Introduction














Summary


H-mode discharge using 3 beam sources and X2 ECCD at

Bt = 3T, Ip = 0.5MA was limited at 40 sec

7

• Bt = 3.0 T (X2 170GHz ECCD), Pext ~ 4.6 MW (PNBI ~ 3.8 MW, PEC ~ 0.8 MW)

• N ~ 1.4, ~ 1.8, ~ 0.6, Vloop = 0.1~0.2 volts

• Discharge stopped by temperature interlock of outer divertor

Lack of X-point control

t=23s t=35s

Outer divertor

Divertor IRTV


H-mode pulse-length at 0.6 MA is extended over 40 s using

only NBI with new divertor striking target

• Ip = 0.6MA, Bt=2T, <ne> ~ 2x1019/m3, N ~ 2.1, tH=43s

• Pext ~ 4.3 MW (ENBI = 95keV/90keV/80keV), Wdia ~ 0.4MJ,

• N ~ 2.1, fNI = 82% (fNB = 63%, fBS = 19%), H89 ~ 1.7

Discharge stopped by PF electricity (MVAr) interlock

D

New target

- Central divertor striking


Increase of plasma current up to 1 MA for 9 sec

- Ip~ 100 kA at the first plasma in 2008

- Ip~ 320 kA with circular plasm in 2009

- Ip~ 900 kA H-mode with 8s in 2012

- Ip~ 1000 kA H-mode with 9s in 2014

- Final goal : 2MA(300s)

• Much efforts on plasma control were devoted to overcome the harsh

disruption events at the high plasma current operation

I MA discharge in 2014


High beta(N~4) above the no-wall limit is

achieved transiently by optimal Ip/BT

Note that the KSTAR key mission is to explore physics and technology

of high performance steady state operation that are essential to ITER

and DEMO.

S. Sabbagh, IAEA 2014

bN /li = 5 bN /li = 4

n = 1 wit

h-wall li

mit

n = 1 no-wall

limit

First H-mode in 2010

Operation

in 2012

Operation

in 2011

Operation

in 2014

• By early heating for low li

• Optimizing BT & Ip

BT in range 0.9-1.5 T

Ip in range 0.4-0.7 MA

• Present maximum bN~4

(transiently) due to lack of radial

control reliability

• KSTAR is ready for RWM

instability study.


More details in Yongsu Na’s talk

Fully non-inductive (overdrive) is achieved

transiently.

q95 ≥ 8.5 for steady-state operation with

high βp at 0.4 MA, 2T

• 𝛽𝑁 ~ 3.0, 𝛽𝑝 ~ 3.5, H89 ~2.2, H98 ~ 1.7

transiently.

• 𝑓𝑁𝐼 = 124%, 𝑓𝑁𝐵 = 72.3%, 𝑓𝐵𝑆 = 51.8% at

𝑛𝑒 0 ~ < 𝑛𝑒 > ~1.1

• No sawtooth instabilities.

• Oscillations due to limitation of the plasma

radial position control.

#10956

0 2 4 6 8 10

-2

0

2

0

1

2

3

0

2

4

0.0

0.2

0.4

0

2

4

6

0

1

2

𝑯𝟖𝟗

𝜷𝑵

𝑫𝜶 (a.

u.)

𝐧𝐞 (#/𝐦𝟑 )

LV (V)

LV (V)

𝐈𝐏

(MA)

𝐏𝐍𝐁 (MW)

𝑻𝒊𝒎𝒆 (𝒔)

Analysis time


Unique features of KSTAR : Low EF and ripple

Ideal machine for 3D & rotation physics

Intrinsically low toroidal ripple and low error field

• Full angle scan shows that the error field would be lower than sub Gauss (resonant

field at q=2/1 based on IPEC calculations)

• Low error field : extremely low value was confirmed (Bm,1/B0~10-5)

• Passing q95=2 (li=0.75) without (violent) MHD

Modular 3D field coils (3 poloidal rows / 4 toroidal column of coils)

• Provide flexible poloidal spectra of low-n magnetic perturbations

Error field scan based on MID RMP coils only


Low EF is supported by accessing low q95 Ohmic

discharges without any external means

The discharge survived near q95< 2

w/o any feedforward or feedback

control of error field / RWM

q95 < 2.0

q95 ~ 3.0

Q95<2.0

800 ms

Indirect evidence of extremely low

intrinsic error field and capability for

extreme operation research in

KSTAR.

• Green : Ohmic discharge reaching q95=2.0

after passing q95=3 (li=1.0) without (violent)

MHD.

• Blue : External error field (Berror/BT~1x10-4)

makes the discharge disrupted (q95 ~3)


Successful ELM suppression using low-n error

field uniquely in KSTAR

Mitigation Suppression

+ + - -

- - + +

- + + -

n=1, +90 phase

+ - + -

- + - +

n=2, even

+ - + -

KSTAR is unique device showing the ELM suppression at n=1 (up to 4s).

• It could related to the low intrinsic error field and low TF ripple.

• According to poloidal phasing, expanded q95 windows for ELM suppression was

tested (q95 = ~ 7.0 at 180 degree, ~6.0 at 90 degree, ~ 5.1 at mixed).

ELM suppression at n=1 (4s) ELM suppression at n=2 (2s)

Suppression


- + + -

Middle only

ELM suppression with only middle coil of n=2 was demonstrated.

• Extension of the ELM suppression requires a stable PCS control to maintain the

narrow operation window of q95(shaping).

• Opens the possibility of tokamak operation by (simple) external coil to the vessel.

2012 (~2s) 2014 (~5s)

Long ELM-suppression period (up to ~5s) is

demonstrated using the n=2 middle FEC coil


OUTLINE

Introduction














Summary


Strategy of the KSTAR research

New Task Forces are formed to support the new strategy and the results will

be used to accelerate the high performance long pulse operation of the KSTAR.

They are:

• Plasma control – expand the operation space of SC device and establish ITER

relevant control

• 3D physics – quantification of confinement characteristics and stability limits based

on the low field ripple and low error field which can be perturbed by IVCC

• Diagnostics – priority on profile diagnostics and improvement/development of new

diagnostics

• Modeling – validation of theory and simulation toward the predictive capability with

sets of advanced imaging diagnostics

• Heating and current drive – improvement of the existing Heating and CD system

and study of new concept for improved efficiency and possible implementation

• Plasma wall interaction and divertor – establish wall conditioning for efficient daily

operation and future steady state operation.


Advanced Plasma Control Task Force

to resolve control issues for advanced scenario

Major roles of APC-TF are

• To resolve several important control issues that are urgent for 2015 campaign

• To establish a tactical plan and framework for advanced tokamak scenario

operations

Reliable & robust

baseline plasma control

(VDE, isoflux etc)

High performance,

steady state operation

Off-normal event &

Disruption control

MHD stability control

(NTM, RWM etc)

Flexible 3D field control

Five tasks defined for APC-TF


Baseline plasma control

Baseline plasma control as the most important task in APC-TF

• Establish a reliable & robust isoflux control scenario

• Re-assessment of vertical stability control under the change of gap-resistance

KSTAR has similar magnetic

control systems with ITER

However, more challenging due

to poor proximity

• Similar configurations of control

coil structure

- Directly applicable to ITER

• Poor proximity of coil-to-plasma in

KSTAR

- More challenging than ITER

ITER

PF1

PF2

PF3

PF4

PF5

PF6

PF7

KSTAR


Baseline plasma control improved significantly,

but marginal vertical controllability

#11660: Long pulse

Reproducible long pulse discharges

achieved

• Not limited by plasma shape control

• Limitations given by PFC temperature

and total apparent power (MVA)

#11721: MA plasma

MA-class discharge achieved

• However, X-point control is still need

optimization

Vertical stability was a severe issue

on attempt of MA-class plasmas

• Vertical stability was marginal

• Thus, the achieved MA discharges

were obtained by reducing plasma

elongation


Improved control for high performance steady-

state operation

Significant and abrupt increases of plasma

performances by the advanced operation scenario Leads

to the fast radial movement

Further decoupling of IP and shape control will be

pursued

New fast radial control by using IRC coils will be

integrated into the baseline plasma control additionally.

IVC (Fast Vertical Control)

IRC (Fast Radial Control)


Real-time control of ECCD power and mirror

position for NTM control

ECCD system is ready for real-time

applications of ST and NTM controls

• Mirror control of 170GHz ECCD

- Mirror response time: 18~20 msec

- Mirror speed: 20 cm/sec

- Vertical position: -25 +45 cm

• Power control of 170GHz ECCD

- Operated up to 50 sec

- Injection power: 0.8 ~ 1.0 MW

Both ‘search & suppression’ and ‘q-

tracking’ control algorithm have been

implemented into PCS and tested


3D physics task force to quantify the confinement

characteristics and stability limits

Mission:

• To investigate and quantify 3D field impacts on transport and

stability, and their limits in KSTAR (uniquely equipped with

extremely low intrinsic error fields and ripples)

3D physics related to transport :

• Energy confinement (E) (or H89 and H98) depends on 3D field

• Momentum transport () depends on 3D field

• Edge transport changes depends on ELM-suppression/mitigation

• 3-D neoclassical transport verification and validation

3D physics related to stability :

• MHD-driven 3D fields and their structures

• MHD spectroscopy

• RMP-ELM control/physics

• Disruption


The low level intrinsic EF may allow us an easy access to

the no-wall stability limit in KSTAR

0

5

10

0 1 2 3 4

B/B0 vs N in KSTAR (measured/linearly projected)

Typical Intrinsic EF level in Ohmic

plasmas

N

B/B0 (x10-5)

bN, no-wall ~ 2.6 (nominal)

Y. In

NF 2014


New installation of the In-Vessel Control Coil

Power Supply for 3D field study

IPS1 IPS4 IPS2 IPS3 IPS5

Top Botto

m Middle IRC

Patch panel IPS Power Supply (5sets)

Poor flexibility and controllability of 3D fields until 2014

• 3 DC power supply with Unipolar operation only

• 3D physics studies were heavily limited due to

configuration change was done by hands and based on

week-by-week change

Upgrade with broadband high speed power supplies

• Output : 500 V, 5 kA,

• Switching freq. : 10 kHz

• Bandwidth : dc ~ 1 kHz

IVCC coil terminals


Newly available features of 3D field control in

2015

B F J N B

: Top-FEC PS1A

PS1B

PS4A

PS4B

: Bot-FEC

: Mid-FEC

PS2B

PS2A PS3B

PS3A

* Fully generalized 3D field configuration *

- Any n(=1 or 2), phase (), and phasing () -

# Predefined 8 sets for 3D field #

Setup Descriptions

STD-N2 Generalized n=2 fields

STD-N1 Generalized n=1 fields with

arbitrary phasing ()

STD-N1A n=1, 90 phasing fields with arbitrary phase

STD-N1B n=1, 180 phasing fields with arbitrary phase

STD-N1C STD-N1 with +90 phase shift

STD-RA Standard RWM control

STD-RB Fully generalized 3D field

STD-RC n=1 phase shooting

Goals • Provide stable operations of new systems (IVCC patch panel + IPSs)

• Provide a flexible and reliable control for newly featured 3D fields

• Real-time feedback of 3D fields such as RWM will be prepared later


Heating and CD TF is to improve the existing

Heating/CD systems and to study new concept

Improvement of existing heating devices

• NBI-1 output power upgrade

• Steady state ECH launcher upgrade

• High power coupling in LHCD (local gas puffing, ne measurement, gap

control, PAM launcher, off-midplane launching)

• Increasing ICRF system efficiency for specific physics topics and IC wall

cleaning (ICWC)

Upgrade (near term)

• Plan of new off-axis NBI for high scenario in near term

• New 3MW, 105/140 GHz ECH system for NTM stabilization and q profile

control

• R&D of helicon wave current drive for high KSTAR operation and leading

research for DEMO


Neutral beam injector worked as a leading heating

and CD source in KSTAR

• Max. injected beam power ~ 4.8 MW

• Longest pulse ~ 45 s at 4.3 MW (80-

95keV)

No. 3 (2014)

No. 1 (2010)

No. 2 (2012)

SECOND

Beam Line

45

cm

13 cm

Long pulse capable Positive ion based ion source

and multi-aperture plasma grid with CuCrZr

1 Beam box with 3 ion sources

Strong on-axis heating & CD (NUBEAM simulation)

Strong central rotation (CES measurement)

• ~250-300 km/s / 4 MW (H-mode) at core

• Te ~ Ti ~ 4 keV / 4 MW (H-mode) at core

1 Beam Box with 3 IS

10 m long BL

NUBEAM simulation peak ~ 0.1


170GHz ECH equipped by CW JAEA gyrotron and

water-cooled launcher

More details in Jinhyun Jeong’s talk

• RF output power (avg.) is 0.91MW at the window

with duration of 50 sec

• Total electrical efficiency is about 40 %

• Maximum collector surface temperature was 150

deg.

• Water cooling temperature saturated during pulse

RF power:

0.8 MW avg. (from diode detector)

VBODY: 24 kV

VK: 48 kV

Beam current:

not stabilized even for overheating

during pulse

Vac. Ion curr. 1.5×10-6 A max.

Temperature of collector surface

VAK: 42.6 45.1 kV (volt. control)

RF power:

0.8 MW avg. (calorimetric)

53 A 41 A

∆T of dummy load ~ 20 deg.

(June 03, 2014)

Water-cooled mirror

(collaboration with PPPL)


Research activities with low power RF Heating &

CD systems

5GHz LHCD system;

• Steady-state PAM launcher design to

support high beta steady state scenario in

KSTAR

• Off-midplane LHCD launching modeling

30-60 MHz ICRF system ;

• IC wall cleaning (ICWC)

• Tungsten coating at the inner conductor in

2015 for increasing of pulse length up to 10

s at maximum 1 MW without arcing inside

VFT

R&D of helicon wave current drive

• for high operation in KSTAR and leading

research for DEMO

30

Simulation of helicon current drive in KSTAR

Tungsten coating at the inner conductor


Plan of off-axis co-tangential NBI (’16 - ’18)

Off-axis neutral beamline

• Two 2 MW off-axis beam sources (+one 2MW on-axis)

• Ion source in vertical plane with longer dimension in

horizontal plane

• All beam-let beam focusing

• Maximum transport efficiency ~ 85%

Preliminary design of off-axis NBI

Co on-axis NBI

Co/counter

off-axis NBI

Ip

On-axis

Off-axis

Off-axis


Goals of H&CD upgrade for high N (4~5) steady

state operation research in KSTAR

On-axis NBI-1 up to 6 MW at ~100 keV (’15-’16)

New off-axis NBI-2 up to 6 MW (’16-’18)

• 4 MW off-axis and 2MW on-axis at 95-100 keV

• Broader j(r) & p(r) for higher N limits

• N ~ 3.5 (with 2.4 MW ECCD)

6 MW ECH

• 3MW 105/140 GHz (’15-’17),

• 3MW 170 GHz (~‘20)

• Increasing flexibility of q(r) tailoring

• Te ~ Ti

• Rotation control, MHD control

4 MW LHCD and 4 MW Helicon (’19-’22)

• Efficient off-axis CD using off-midplane PAM

and TWA antenna

• N ~ 4-5 (RS with qmin > 2)

All long pulse capable up to 300 s

Off-midplane

5 GHz LHCD

0.5 GHz

Helicon

Off-axis NBI configuration

GENRAY

n//0 = 2.5

Bt = 2 T

TH2178,

500MHz,

0.8MW

CW

E3732,

508MHz,

1.2MW

CW

CURRAY


PWI task force to solve physics issues related to

PSI during long pulse steady state operation

Short pulse operation

Heat Flux Control

Density Control

Long Pulse Steady

State Operation

Impurity Transport

Control

Neutral Pressure Control

Wall Conditioning

Heat Load on PFCs

PFC Material Development

PFC Shaping

Impurity Source

Impurity Migration

Core accumulation/Removal

Fuel Retention

ISSUES


Preparation of the in-vessel components for

longer pulse operation

Passive stabilizer

structure upgrade

(‘14)

Preparing for liquid helium

circulation into cryopump

(‘16) Heat load on “naturally

misaligned W-tile castellation”

Active water cooling in

divertor & limiter (‘15)

ICWC between shots (‘14~)

Pellet injector (‘16)

IVCC power supply (IPS)

upgrade


Wall conditioning under TF field using IC wall

conditioning 35

Wall conditioning & Particle Control

• Long-pulse discharge leads large amount of retention in 2014

• Inter-shot He ICWC could reduce the accumulated retention and maintain the

retention low during a day

Accu

mu

late

d r

ete

nti

on

Shots with ICWC Accu

mu

late

d r

ete

nti

on

Shots with ICWC

Nov. 25 Nov. 26 Nov. 27


Heat load on divertor according to ELM control

w/o RMP w/ RMP

A B

Temperature(oC)

KSTAR Div. IRTV #10880 (tm

= 6.0534 sec, tep

= 0.5 ms)

80

100

120

140

160

180

200

220

240

260

0 20 40 60 80 100 120 1400

1

2

3

4

Distance [mm]

Heat

flux

[MW

/m2]

A B

Temperature(oC)

KSTAR Div. IRTV #11211 (tm

= 10.7668 sec, tep

= 0.5 ms)

60

80

100

120

140

160

180

200

220

240

260

0 20 40 60 80 100 120 1400

0.5

1

1.5

2

2.5

Distance [mm]

Heat

flux

[MW

/m2]

1st maximum

2nd maximum

• Splitting the peak was found when RMP was applied.


Diagnostic systems upgrade for steady-state

operation

Control related diagnostics

• For real-time measurements

• MD, Interferometer (+ECE, MSE)

• Ground system will be rearranged for decoupling of the system noise

• Fast sampling FPGA (100MHz) will be adopted for real-time fringe-jump correction

in interferometer.

Profile diagnostics

• To provide reliable & comprehensive profile data for physics study

• TS, ECE, CES, XICS, MSE

• Proto-type ITER laser for TS will be returned / new commercial laser will be installed

• For S/N improvement in TS, baffle installed on input port and EMI shield covers

• MSE system will be commissioned in the coming 2015 campaign

Two-dimensional diagnostics

• for validation of the modelling , theories & simulation

• ECEI, MIR, BES (+IR TV)


Front optics inside cassette PEM Mirror

Beam splitter

MSE

CES

Top view

19 fibers per channel (600 um)

• 25 channels / 1 ~ 3 cm spatial resolution • Polarization-preserving collection optics shared with Charge-Exchange Spectroscopy (CES) • To solve spectral overlap of three ion sources, Stark spectrum was simulated for required

filter parameter & operating range

New diagnostic system : Motional Stark Effect

(MSE) is installed for q profile measurement


Modeling task force

Mission:

• Lead experimental analysis using various simulation

codes and theoretical models

• Facilitate interaction between simulation and diagnostic

development

• Promote domestic & international collaborative researches

for simulation and analysis of KSTAR experiment

2015 experimental plan related to transport :

• Dedicated experiments for gyrokinetic code validation

• Develop target discharges with a single dominant

fluctuation population (either TEM or ITG)

2015 experimental plan related to MHD :

• H-mode with clear inter-ELM MHD activities

• H-mode with on-axis ECH to study internal kink

• Tearing mode control with resonant / non-resonant 𝛿𝐵

BOUT++ simulation of RMP

response in KSTAR


Operation plan of KSTAR 2015 campaign

Extension of H-mode plasma operation range

• H-mode ~ 60 s at 0.5 MA, ~ 20s at 1 MA,

• 3D physics & ELM control (~ 10s)

• Reliable operation of advanced tokamak operation (high beta, non-inductive)

System maintenance and upgrade

• IVCC power supply (broadband) : 5 kA, 10 kHz, 0.5 kV, 5 set

• ECH/CD extension : 1 MW, 105/140 GHz

• PWI : Active cooling in PFC/Divertor, ICWC between shots

• Diagnostics : MSE, Thomson laser, etc.

FY2014 1 2 3 4 5 6 7 8 9 10 11 12

Schedule of 2015 campaign

Plasma experiments

Evacuation, wall conditioning

Machine commissioning

Magnet warm-up

Maintenance & upgrade

Magnet cool-down

Research Forum


Superconducting

Tokamak operation

Long-pulse H-mode

and ITER pilot

Advanced scenario

related to DEMO Advanced Technology

for K-DEMO

Phase I (FY08 ~ FY12)

• Integrated control of

SC tokamak

• First plasma

• H-mode discharge

• Experimental

collaboration

Phase II (FY13 ~ FY17)

• ITER priority research

(ELM, Disruption, NTM)

• High performance

plasma study using

KSTAR intrinsic tools

(intermediate heating

power, low density)

Phase III (FY18 ~ FY22)

• Advanced operation

scenario demonstrate

• Integrated control of

profile and stability

• Research application

to K-DEMO

Phase IV (FY23 ~ )

• Stabilization and

optimization of

advanced scenario

• Technologies at

extreme

environments

Research under long-pulse H-mode discharge

•Plasma operation ~ 1 MA, 50 s, betaN ~ 2

•Heating/CD : ~ 15MW

- NBI ~ 10MW (4 MW off-axis)

- ECH/CD ~ 3MW

- RF (ICRF, LHCD, Helicon) ~ 2 MW

•Divertor/PFC : active cooled graphite tile

•Density : pellet & cryopump

•Stability control : ELM, disruption, NTM

•Electric : grid 100 MVA + MG 200 MVA

Research under advanced steady-state operation

• Plasma operation ~ 2 MA, 300 s, betaN~4

• Heating/CD : ~ 28 MW

- NBI ~ 12 MW

- ECH/CD ~ 6 MW

- RF (ICRF, LHCD, Helicon) ~ 10 MW

• Divertor/PFC : detached divertor & new material

• Density : pellet & cryopump

• Stability control : NTM, RWM

• Electric : grid 100 MVA + MG 200 MVA

Long-term operation plan of KSTAR


We appreciate the strong contribution on the engineering or physics

research in KSTAR from the domestic and international collaborators.

Collaborators

Korea Asia & Australia America Europe and Russia

• NFRI

• KAERI

• Seoul Nat’l U.

• KAIST

• UNIST

• POSTECH

• Hanyang U

• Daegu U.

• Ajou U.

• Jeju Nat’l U.

• Yonsei U.

• Dankook U.

• Kyungpook Nat’l U.

• Chungnam Nat’l U.

• UST

• NIFS

• JAEA

• ASIPP

• HUST

• IPR

• SWIP

• Nagoya U.

• Kyushu U.

• Australia Nat’l U.

• PPPL

• General Atomics

• ORNL

• Columbia U

• MIT

• UC Davis

• Maxplanck IPP

• CEA

• CCFE

• ENEA

• TU/e

• York U

• EURATOM-FOM

• Karlsruhe Inst. Of

Technolegy

• Politecnico di Torino

• Kurchatov Inst

• ITER


Summary

KSTAR showed remarkable progress in the long-pulse H-mode discharge

over 40s at 0.6 MA and increased current operation up to 1 MA.

High performance operations were achieved transiently such as high N

(~4.0) operation, fully non-inductive scenario (fNI ~ 124%).

The unique features of the KSTAR such as extremely low intrinsic error

field and low TF ripple could enables research exploring the limits of

confinement and instability.

In preparing the KSTAR 2015 campaign, six TFs are organized to support

the new strategy and the results will be used to accelerate the high

performance long pulse operation of the KSTAR.

This work was supported by MSIP under KSTAR project and was partly

supported by the NRF under A3 Foresight Program (No. 2012K2A2A6000443).

44

Thank you for your attention !

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감사합니다 (gamsa ham nida)Ko, ありがとうございます(arigato gozaimasu)Ja, 谢谢(xie xie)Ch,

शुक्रिया (sukriya)Hi, спасибо (spasibo)Ru, DankeGe, merciFr, köszönömHu,

graciasSp, grazieI, obrigadoPo, ُشْكًرا) (shúkraan) Ar

status of the advanced research under long-pulse operation in … · 2015-05-27 · status of the...

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