Plan for 20092010 July 27 2009 M Kwon and the KSTAR Team National Fusion Research Institute EPICS Technical Meeting NFRI July 2729 2009 Outline Introduction Operation result in 2008 ID: 314597
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Slide1
KSTAR Operation Status and
Plan for 2009-2010
July
27
2009M. Kwon and the KSTAR TeamNational Fusion Research Institute
EPICS
Technical
Meeting
,
NFRI
,
July
27-29,
2009Slide2
Outline
Introduction
Operation result in 2008
Operation plan for
2009-2010
Longterm PlanKSTAR CollaborationSummarySlide3
KSTAR objectives and parameters
To develop a steady-state capable advanced superconducting
tokamak
To establish the scientific and technological base for an attractive fusion
reactor as a future energy source
Major radius,
R
0
Minor radius,
a
Elongation,
Triangularity
,
Plasma volume
Plasma surface area
Plasma cross section
Plasma shape
Plasma current,
I
P
Toroidal
field,
B0 Pulse lengthN Plasma fuelSuperconductorAuxiliary heating /CDCryogenic
PARAMETERS
1.8 m0.5 m2.00.817.8 m3 56 m2 1.6 m2 DN, SN2.0 MA 3.5 T300 s5.0H, D-DNb3Sn, NbTi~ 28 MW9 kW @4.5K
KSTAR
6.2 m2.0 m1.70.33830 m3 680 m2 22 m2 SN15 (17) MA5.3 T 400 s 1.8 (2.5)*H, D-TNb3Sn, NbTi73 (110) MW
ITER
* M. Shimada, et al., Nuclear Fusion, vol. 47, pp. s1 (2007)
KSTAR & ITER
KSTAR Parameters
KSTAR missionSlide4
Status of the KSTAR
tokamak
in 2008
KSTAR tokamak
Helium distribution system
Supercritical, 4.5K, 600 g/sVacuum pumping system
VV : 42,400 l/s,
Cryostat : 36,900 l/s
ICRH
30~60MHz, 2 MW, 300s
ECH
84GHz, 500kW, 2s
TV
ECE
Visible spectroscopy
H
Filterscope
mm-wave interferometer
Movable hall probeSlide5
Status of the KSTAR
tokamak
July 10, 2009
New Deck for
Movable Prove and XCSSlide6
Minimum
in-vessel components
were installed for the first plasma.
In-vessel components 2008
ICRH antenna
ECH antenna
Movable hall probe
Inboard limiter
Poloidal
limiter
Glow discharge,
Gas injection
Magnetic Diagnostics
Rogowski
coils
Vessel
curent
monitor
Diamagnetic loop
Flux loop
Magnetic probes
Hall probes
Optical Diagnostics
Visible camera
H
Visible spectroscopy Filterscope ECE mm-wave interferometerSlide7
Most of Magnetic Diagnostics , Full scope of Inboard Limiter
In-vessel components 2009
Inboard limiter
Inboard Limiter BoundarySlide8
In-Vessel Component
1
2
2
3
5
4
6
7
1
Inboard Limiter (
2009
)
2
Divertor (for double null, 20 sec,
2010
)
3
Passive Stabilizer (
2010
)
4
Poloidal Limiter (
2010
)
5In-vessel control coil (2010)6NB armor (NBI-1, Port L, 2010)7
In-vessel Cryopump (2010 ~ 2011)Slide9
Upgrade Sequence of In-Vessel Component
9
1
2
3
4
5
6
7
8
Partial Installation of the Inboard Limiter
Full Installation of the Inboard Limiter
Installation of the IVCC
Installation of the Divertor System
Installation of the NB Armor
Installation of the Passive Stabilizer
Installation of the Poloidal Limiter
Upgrade for 300sSlide10
Operation results in 2008Slide11
Startup scenarios
Startup scenarios were prepared considering the limited capacity of power supply.
Compared between conventional
&
dipole like start up scenariosECH pre-ionization2nd harmonic ECH pre-ionization was achieved at 1.5 T reduced TF field.
Due to ECH pre-ionization, required loop voltage could be lowered to about 2 V.1st harmonic ECH pre-ionization at 3.0 T is planned in 2009.
Startup scenarios and ECH pre-ionization
worked well.
Plasma discharge
Startup scenario
Shot 558
TF = 13.3kA (1.5 T @ 1.6 m)
ECH = 84 GHz, 500kW, 50ms,
Shot 977
TF = 14 kA (1.5 T @ 1.7 m)
ECH : perpendicular launch
ECH pre-ionization test
under TF field only
ECH pre-ionization test
at dipole-like field configurationSlide12
KSTAR succeeded achieving reproducible
tokamak
plasmas
with
strict h/w limits of 1.1 Wb in the first trial by combining a unique magnetic configuration and 2nd harmonic ECH preionization,
Circular ohmic plasma discharge (ECH assisted)Hydrogen plasmaFirst plasma (107 kA, shot No. 794) was achieved on June 13, 2008.
The target of first plasma was achieved.
Plasma discharge
ECH assisted
ohmic
plasma discharge
Basic plasma parameters for first
plasmnaSlide13
ECH
pre-ionization
study (ITPA HPRT)
Pre-ionization study
in terms of
beam
launch direction
ECH pre-ionization test according to beam launch directions
Toroidal
scan : normal,
co- and counter-oblique
injection (+10
0
~ -10
0
)
Vertical scan : (z= +10 ~ -10 cm)
The pre-ionization of oblique beam launch
was
more efficient than the perpendicular
launch
.
ECH antenna
- mirror pivot
R=2800
y=-252 x=-279BtIpNm-portCo-injectionCNT-injection
ECH launch directions
Pre-ionization according to beam launch directionSlide14
ECH
pre-ionization study
ECH power
threshhold
for 2nd harmonic plasma breakdown was about 280 kW.
At least 320 to 350 kW of ECH power was needed for reliable breakdown in KSTAR 1st plasma campaign. The plasma breakdown time has been reduced with higher ECH power.
280 kW(#1078, black)
320 kW(#1079, red)
350 kW(#1080, blue)
ECH pre-ionization according to ECH power
Pre-ionization delay time
No
breakdown
(P
ECH
: 280 kW)
Pre-ionization study
in terms of
beam
powerSlide15
Shot 1127 @ t=543.1
msec
I
pl,mea
= 97.1 kA, Ipl,rec=98.3 kA, Ivv = 59.3 kAzout = -9.1 (cm), Rout = 161.2 (cm), a = 35.2 (cm)
zc = -9.3 (cm), Rc = 164.9 (cm) Good condition no. (7.84 e3) Using all MP’s and FL’s with optimized fitting weight Vacuum vessel and real limiter structure are considered Good agreement with CCD camera
EFiT
Reconstruction
Plasma Current
Zout
RoutSlide16
- The effect of Incoloy is not included
By O. Hopkins
EFiT
Reconstruction
Shot 1127Slide17
Issues for KSTAR
magnetics
KSTAR has an inherent source of magnetization inside the PF & TF coils
Incoloy
908 is the jacket material for superconducting strand Weakly ferromagnetic with max μr~10 (saturation B~1T) Toroidally symmetric but problematic for field-null qualityExperimental findings : Downward shift of plasma Lower measured loop voltage than the calculated by the circuit equations PF coil currents decay faster than the calculated by the circuit equations
=> Need additional up-down asymmetric sources of current and fieldCryostat is a potential source of up-down asymmetry Large current at the lower cryostat will drive plasma downward Other discrepancy might be due to cryostat current also
Incoloy
908
Understanding MagneticsSlide18
A genuine reconstruction code has been developed
to cope with nonlinear magnetization from
Incoloy 908 in CICC and
partially validated with the measurementsstill require better understanding of the magnetic probe measurements and its validation still large discrepancy between the measured and the calculated vessel currentdeveloped analysis tools are directly applicable to ITER TBM analysis
The cryostat is a potential source of up-down asymmetryaccording to the calculations, rather large current flows in the cryostat(~200kA)better agreement with loop voltage measurements with the cryostat circuitpotentially problematic in ITER also
By upgrading and
thorough
validation of the magnetic diagnostics
in next
campaign, these issues will be examined in more quantitative way
Understanding MagneticsSlide19
DC glow discharge cleaning
Glow discharge at zero field condition
at night (H
2 & He)RF discharge cleaning between shots
DC glow is not acceptable due to continuously applied TF field.KSTAR ICRH system (2 MW, 300 sec, 25 -60 MHz) used for discharge cleaning between shots at 30 kW (30 MHz).2 seconds pulse in every 12 seconds for 5-10 minutes just after plasma shot .Wall conditioning (ITPA HPRT)
DC glow discharge using the probe
RF discharge using the ICRF system
Two kinds of discharge cleaning methodsSlide20
Line density variation due to ICRH
He cleaning
ICRH(He)5min
Between shots
Line density decreases
shot by shotICRF-DC was successfully started without major fault due to the appropriate protection system.Line density was affected by the shot to shot discharge cleaning.Exact assessment of residual gas variation due to DC was difficult due to background signals from the pumping lines in RGA system.
Quantitative measurement of wall condition is required with
better-set RGA
system and increasing pulse length of RF power.
RF discharge cleaning effects
856
857
858
RGA signal during DC and plasma shots
Wall conditioningSlide21
Dust
collection
and
analysis
Dust generation was often
observed by visible CCD cameras.Cause : change of heating directions, plasma movement, etc. Events from in-board limiter and MD protectionsCollected dusts at 10 different in-vessel positions using sticky carbon tape.
Large dispersion: 100nm-20um.
Two major peaks at ~100 nm and 2um.
Detected components: C, Si,
Mn
, P, S, Ni, Cr,
Fe
,
Cl
, Ag, Al, Mg
Inboard limiter,
Diagnostics (mirror, etc)
Dust collection and analysis was
possible from
the virgin operation.Slide22
Most of the
targeted values of the 1
st
campaign
were achieved.
Results of the 2008 campaign
Classifications
Target
Achieved
Remarks
Final
Spec.
∙
VV base
pressure
∙
Cryostat base pressure
∙
Total
leak rate
≤ 5.0x10
-7
mbar
≤ 1.0x10
-4
mbar≤ 1.0x10-4 mbar·l/s3.0x10-8 mbar3.0x10
-8 mbar1.7x10-7
mbar·l/sOKOKOK∙SC coil temperature∙Thermal shield temperature (In/out)∙Temperature distribution≤ TF & PF : 5 K≤ 55 / 70 K≤ 50 KTF & PF : 4.48 K51 / 72 K48 KOK
OKOK
∙SC transition temp.∙Joint resistance∙Coil insulation∙TF current ∙TF field at major radius∙PF coil current∙PF Blip periodNb3Sn : 18.3 KNbTi : 9.2 K ≤ 5 nΩ> 100 MΩ≥ 15 kA≥ 1.5 T4 kA≥100 ms
Nb
3Sn : 18±0.2 KNbTi : 9.9±0.1
K
0.5 ~ 2 nΩ> 3,000
MΩ15 kA
1.5 T
4 kA
50 ～ 150 ms
OK
OK
OK
OK
OK
OK
OK
OK
35
kA
3.5 T
25
kA
∙
ECH
for pre-ionization
∙
Plasma current
∙
Plasma duration
∙
Plasma
duration
≥
100 kA
≥ 400 kW (0.2 s)
≥ 100 kA
≥ 0.1
s
480 kW (0.4 s)
133 kA
0.8
6
s
0.33 s
OK
OK
OK
OK
2,000 kA
300 s
300
sSlide23
Operation plan in 2009-2010
Vacuum pumping system operation
Cryo
-facility
operation
Superconducting State
Plasma Exp.
Pumping down / Leak check / Wall conditioning
Cool-down from 300 K to 4.5 K and
warmup
Maintain 4.5 K Slide24
Available operation time in 2009-2010
2009 Operation
2009
1
2
3
4
5
6
7
8
9
10
11
12
2010 Operation
2010
1
2
3
4
5
6
7
8
9
10
11
12
IAEA FEC
In Korea
Vacuum & wall conditioning
Cool-down &
warmup
SC magnet operation
Plasma exp.
Vacuum & wall conditioning
Cool-down &
warmup
Plasma exp.
H/W upgrade
H/W upgrade
SC magnet operationSlide25
System availability for 2009-2010 operation
2008
2009
2010
SC Magnetic system
TF coilsPF coils & leads
15 kA
4 kA
unipolar
Up/Low series
35 kA
4 kA bipolar
Up/Low
series
35 kA
20 kA bipolar
Up/Low separate
(4 more PF PS)
In-vessel system
In-vessel coil
PFC
Wall conditioning
Inboard
limiter
Glow DC, RF DCInboard limiters+ boronizationVertical controlDivertor / limitersPassive stabilizer
+ PFC bakingHeating system
ECHICRHNBILHCD0.5 MW (84 GHz)0.03 MW (30 MHz)0.5 MW (84 GHz)0.3 MW (45 MHz)0.5 MW (84 GHz)0.5 MW (110 GHz)1 MW 1 MW0.5 MWInfra systemGrid Power50 MVA (154 kV)50 MVA (154 kV)100 MVA (154 kV)Slide26
Operational parameters in 2009-2010
2008
2009
2010
Experimental parameters
Peak TF fieldOperation TF field
Flux
Ip
Plasma shape
Gas
1.5 T
1.5
T
~ 1
Wb
< 133 kA
Circular
H
2
(He for DC)
3.5 T
1.5
T, 3.0 T
~ 2
Wb
~ 300 kACircularH2 (He for DC), D23.5 T1.5 T, 2.0 T, 3.0 T~ 4 Wb< 1 MADouble nullH2, D2Control
Plasma control
PF blip & start upIp, Rp , nePF zero-crossingIp, Rp, neIVC controlIp, Rp, Zp, shapeDiagnostics Diagnostic systemsMD/ MMWI/ ECE / Hα/ filterscope/ ViS . TV• MD/ MMWI / ECE / Hα/ filterscope/ Vis. TV• PD / XCS / Soft X-ray / Reflect./ XCS (1 set) / Bolometer (resistive) /• MD / MMWI / ECE/ Hα/ filterscope/ Vis. TV
• PD / XCS / Soft X-ray / Reflect. • TS/ Hard X-ray / Fast neutral / ECEI / IRTV/Fast Ion Loss DetectorSlide27
FY 2008
FY 2009
FY 2010
FY 2011
FY 2012
Operation
(
Vac,CD
& WU)
‘08. 3 ~ ‘08. 8
(6
mon
.)
‘09. 8 ~ ‘09.12
(5
mon
.)
‘10.6 ~ ‘10. 11
(6
mon
.)
‘11. 4~ ‘11. 9
(6
mon
.)
‘12. 2 ~ ‘12. 7 (6 mon.)Experimental GoalsFirst plasma startup2nd Harmonic ECH pre-ionization1st Harmonic ECH Pre-ionizationStartup stabilization
Shaping
control & vertical stabilizationHeating Confinement (L-H)StabilizationHeatingPlasma–Wall InteractionProfile controlRWM, ELM controlOff-axis current driveTargetOperation ParametersBT ~ 1.5 TIP > 0.1 MAtP > 0.1 sTe > 0.3 keVTi ~ 0 keVFlux ~ 1 WbShape ~ CircularGas : H2BT ~ 3 T
IP > 0.3 MA
tP > 2 sTe > 0.3 keVTi ~ 0.3 keVFlux ~ 2 WbShape ~ CircularGas : H2,, D2BT ~ 3 TIP < 1 MAtP ~ 10 sTe ~ 1 keVTi ~ 1 keVFlux ~ 4 WbShape ~ DN(double null)Gas : H2, D2
B
T ~ 3 TIP < 1.5 MA
t
P ~ 10 sTe ~ 1 keV
Ti ~ 3 keVFlux ~ 6
Wb
Shape ~ DN & SN
Gas : D
2
B
T
~ 3 T
I
P
< 2
MA
t
P
> 100 s (0.5 MA)
Te ~ 1
keV
Ti ~ 5
keV
Flux
~ 8
Wb
Shape ~ DN & SN
Gas : D
2
PFC & Wall conditioning
Inboard
limiter (belt)
Gas puff
Inboard limiter (w/o
cooling
)
Boronization
Divertor
/ Passive plate
PFC baking
In-vessel coil
Cryopump
operation
PFC cooling
PFC cooling
Pellet
Magnetic
control
TF : 1.5 T
PF : 4 kA
unipolar
TF : up to 3.5 T
PF : +/-4 kA
TF : up to 3.5 T
PF : +/-10 kA
IVCC : VS, RS
TF : up to 3.5 T
PF : +/-15 kA
IVCC : FEC. RMP
TF : up to 3.5 T
PF : +/-20 kA
IVCC : RMP, RWM
Heating operation
ECH(84G): 0.5MW, 0.4s
ECH(84GHz): 0.5MW,
2s
ICRH(
45MHz
): 0.3MW, 10 s
ECH(84/110GHz): 0.5MW
ICRH(45M
Hz
): 1MW, 10 s
NBI: 1.0MW, 10s
LHCD: 0.5MW, 2s
ECH(84/110GHz): 0.5MW
ICRH(45M
Hz
): 2MW, 10 s
NBI: 2.5MW, 10s
LHCD: 0.5MW, 2s
ECCD(
170G
Hz
):
1MW, 10s
ECH(84/110GHz): 0.5MW
ICRH(
45M
Hz
): 2MW,
300 s
NBI
:5
MW, 300s
LHCD : 1MW, 2s
ECCD(1
70G
Hz
):
1MW, 300s
Diagnostics
MD (77 Ch)/ MMWI / ECE / H
/
filterscope
/ VS / TV
MD/ MMWI / ECE / H
/
filterscope
/ VS / TV
PD /
XCS (1 set) / Bolometer (resistive) / Reflect. / Soft X-ray
MD / MMWI / ECE / H
/
filterscope
/ VS / TV
PD /
XCS / Bolometer / Reflect. / Soft X-ray
Thomson Scattering / Hard X-ray / Fast neutral / IR TV / ECEI
MD / MMWI / ECE / H
/
filterscope
/ VS / TV
PD /
XCS / Bolometer / Reflect. / Soft X-ray
TS / Hard X-ray / Fast neutral / IR TV / ECEI
MSE / FIR / CES / neutron
MD / MMWI / ECE / H
/
filterscope
/ VS / TV
PD /
XCS / Bolometer / Reflect. / Soft X-ray
TS / Hard X-ray / Fast neutral / IR TV / ECEI
MSE / FIR / CES / neutron / VUV
MIR
/ BES / CI /
Near-term experiment planSlide28
Research topics in 2009-2010
Power supply control
TF magnet test up to 35 kA ; B
TF
up to 3.5 Tesla @ R=1.8m
PF magnet & power supply control for zero-crossing : Flux up to 2 WeberVertical & radial stability control using IVCC (‘10) Plasma controlPlasma current and position control (Ip, Rp
)
Plasma shape control (
Rp
,
Zp
,
kappa, delta) (‘10)
Magnetic probes & analysis
Refined characterization of the
magnetics
with additional sensors and electron beam system. (quantifying field errors, calibration of magnetic probes)
Understanding the material (Incoloy908) and geometry effects on plasma
MagneticsSlide29
Research topics in 2009-2010
ECH pre-ionization
Full exploitation of 84 GHz &
110 GHz
Gryotron
Further Investigation of ECH assisted pre-ionizationDependence on 1st & 2nd harmonics, injection directions
ICRH heating and RF discharge cleaning
Exploitation of ICRH heating
Exploit RF discharge cleaning between shots
Commissioning of additional heating
hevices
NBI (1 MW), LHCD (0.5 MW) (‘10)
Heating researchesSlide30
Research topics in 2009-2010
Wall conditioning & wall interaction
Quantitative approach on wall conditioning & wall recycling
Hydrogen recycling/retention under different wall condition(
Boronization
, RFGDC, ICRH DC)Characterization of the dust behaviorExperimentsDisruption studiesPossible MHD Studies ;
sawtooth
manipulation, locked
mode
Experiments based on the collected proposals (domestic /international)
Data access and collaboration
Data access, analysis, logging
Remote experiments participation & operation
Other researchesSlide31
Experimental Proposals
37 experimental proposals registered through internet
In 7 categories
System commissioning (5)Magnetic configuration and equilibrium reconstruction (7)
Startup and current ramp-up (4)Diagnostics (4)Heating and current drive (3)Wall conditioning (3)Instabilities (7)Transport and confinement (4)28 domestic / 9 international NFRI (18) Postech (7)
KAERI (3)GA (5)PPPL (2)ORNL (1)Far-Tech (1)Slide32
Remote Experiment (2009, Collaboration with GA)
discussion
discussion
KSTAR site
RSL
H323
Non-PCS parameter confirm
PCS
parameter
input
PCS
Confirm
“Next Shot is ready”
DSL
CMO
Y
N
Run Shot
parameter
Input
/ limit check
Result transfer
Shot analysis
Shot log
Wait for live shot updates
Shot summary put to web portal
EPICS / H.323
MDSplusRemote siteAuthorizationtoolsDeputy session leader (DSL)Remote session leader (RSL)Chief Machine Operator (CMO)Local operators
Assistant
PhysicsOperatorConnection / transferSupportH323 video.PCS remote GUIWeb logbook & summaryPCS wave server RDB serverElectronic authorization layer MDSplusSlide33
Long-term Operation planSlide34
Operation target by 2012
H-mode operation control
Plasma wall interaction research
FEC and RWM control with
ELM suppression using IVCCNTM suppression with ECCD
Key milestones
Physics targets
1
st
KSTAR operation
phase ends
Achieve knowledge on
supeconducting
tokamak
characteristics for H-mode operationSlide35
Long-term plan (mainly by 2017)
Physics target
Targetted
for a milestone of ITER construction completionPlays a role as an
ITER pilotSteady-state operation control H-mode plasma stabilization for long pulseAT mode (high beta) operation achievement with available heating systemsSlide36
Long-term experiment planSlide37
EU Support & Collaboration
Domestic Core Research Centers
World Leading Experts
(International)
Fusion R&D Collaboration (International)
KSTAR Collaboration Framework
EU-WLEs
US-WLEs
JA-WLEs
Profile Diag.
Visualization
(POSTECH)
Reactor Engineering
(SNU)
Heating & CD
(KAERI
)
Edge Diag.
(
Hanyang
U.)
Divertor
& Simulation
(KAIST)
International Collaboration and Experts Participation
ITER Pilot R&D
ITER-IO
Simulation R&D
SciDAC
(US)IPERC (JA), etc.Co-ExperimentsITER MembersNon-ITERUS Support & Collaboration JA Support & Collaboration Slide38
Summary
KSTAR
first-plasma milestone
achieved,
even
with limited hardware capabilities in wall-conditioning, diagnostics, power supply systems etc.2008 operation campaign was accomplished in 5 months without any serious fault. International collaborations were essential to achieve the milestones.To get meaningful results in 2009 & 2010 campaign,Acceleration in hardware upgrade,
Careful system operation and concentrated experiment plan,
Accurate measurement and in-detail understanding on SC
tokamak
operation, and
Stronger domestic and international collaboration are required
.
KSTAR control system played a key role to achieve
first-plasma
milestone.Slide39
Thank you for your attention !
At the beginning of the KSTAR cool-down (April. 3, 2008)