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Operation Phase(2008~)

About KSTAR

KSTAR is the worldclass superconducting tokamak developed and constructed by domestic technology. The knowledge-base for fusion science and operation technology will be established through the operation of KSTAR. A world-leading position in fusion technology will be attained in the era of commercial fusion power plants.

KSTAR Mission & Progress

KSTAR Mission & Progress

KSTAR Key Features

KSTAR Key Features

KSTAR Parameters

KSTAR Parameters

Main Structure

Main Structure
Main Structure
Visible spectroscopy
Filterscope
Ha
ECE
mm-wave interferometer
Movable hall probe
TV
  • ECH
    84GHz, 500kW, 2s
  • ICRH
    30~50MHz, 2MW, 300s
  • Vacuum Pumping System
    VV: 42,400 l/s
    Cryostat : 36,900 l/s
  • Helium Distribution System
    Supercritical, 4.5K, 600g/s
Superconducting Tokamak

The Superconducting Magnet system consists of 16 TF(Toroidal Field) coils and 14PF(Poloidal Field) coils. Both of the TF and PF coil system use internally cooled superconductors. The TF coil system provides a field of 3.5 T at a plasma center, with a peak flux density at the TF coils of 7.5 T and the stored energy is 470 MJ. Incoloy 908 conduit and Nb3Sn superconducting cable are used for the TF CICC. The nominal current of TF coils is 35.2 kA with all coils in series. The PF coil system provides 17 V-sec and sustains the plasma current of 2 MA for 20 seconds inductively which consists of 8 coils in the CS(Central Solenoide) coil system and 6 outer PF coils. PF 1-5 coils use Nb3Sn CICC in Incoloy 908 conduit and PF 6-7 coils use NbTi CICC in a modified stainless steel 316LN.

Superconducting Tokamak

Ancillary Systems

Ancillary Systems
  • C.W Chiller
  • Cooling Tower
  • Magent Power Supply
  • 22.9kV Power Distubution
  • 15kV somva
  • ECH heating System
  • Control Room
  • Helium Refrigerator
  • Helium Comprossor
Internal Floor
F3
  • He Distribution System
  • Cryogenic System
  • Diagnostic DAQ System
  • ECH System
F2
  • ICRH System
  • Vacuum Pumping System
F1 Fueling/Glow Discharge
B1
  • Tokamak Monitoring System
  • Quench Detection System
B2
  • Current Lead System
  • Magnet Power Supply

Diagnostics

Diagnostics
    • Basic Diagnostics
    • BaselineⅠ
    • Baseline ⅡⅢⅣ
    • MD Feedthough Inspection Illuminator Visble/H-alpha Tv
    • Edge reflectometer
    • Survey IR TV CES Background Escaping fast-ion detector
    • X-Ray Crystal Spec.
    • Thomson scattering(beam dump)
    • Recip. Lanmuir Probe(Movable) X-Ray Pinhole Camera
    • Visible/H-alpha TV
    • Soft X-Ray Array Bolometer Array
    • survey IR TV X-Rah PHA Impurity Pellet Unjector
    • MD feedthrough nspection Illuminator Survey IR TV
    • Movable Lanmuir Probe
    • X-Ray Crystal Spec.
    • Soft X-Ray Spec. VUV Survey Spec.
    • MM-Wave Interferometer
    • Reflectometer
    • MIR/ECEI
    • Tangential FIR Interferometer(Iaser input)
    • MD Feedthrough Visible/H-alpha TV Inspection Illuminator
    • Visible Survey Spec.
    • H-alpha Monitor
    • Visible Brem. Array Visble Filterscope
    • ECE Hetero. Radiometer
    • ECE Grating Polycromator Diag. Neurtral Beam LIF(optics)
    • Bolometer Arry
    • Thomson Scatt. Laser input CX-NPA
    • MD Feedthrough Inspection Iiiuuminator
    • CES/MSE/BES
    • Thomson Scatt Divertor Thomson(optics)

Heating Devices

Heating Devices

Heating Devices : Heating and current drive Tokamak fusion device in the device as a device as necessary for the fusion reaction plasma ion and electron temperature for heating and for the continuous operation of tokamak devices, non inductive current drive, current profile control for high-performance operation, fusion plasma MHD instabilities, such as the control of several important functions

  • NBI(Neutral Beam Heating) : Ion heating
  • ICRF(Ion Cyclotron Range of Frequency) : Ion & electron heating
  • LHCD(Lower Hybrid Current Drive) : Electron heating
  • ECH(Electron Cyclotron Heating) : Plasma startup & Electron heating
  • NBI-2(2017~2020) (6MW, 300s) - co, CNT(underconsideration
  • NBI-1(2010~2014) (8MW, 300s)
  • Start-up ECH(0.5MW, 2s 84GHz)
  • ICRF(2MW, 300s, 30-60MHz)
  • LHCD(2011~2016) (2MW, 300s 5GHz)
  • Heliumtransferline
  • Heliumdistributionbox
  • ECCD(2011~2015) (3MW, 300s, 170GHz) (Iauncher development with PPL)
  • Cryostat pumping duct
  • VV pumpingduct

KSTAR operation & experimental plan

KSTAR will be one of the most effective devices for ITER relevant operation and physics for reliable fusion reactor.

  • Accumulation of the technical know-how for the superconducting tokamak operation
  • Leading the high performance steady-state plasma experiment
plasma experiment
Phase PHASE1 PHASE2 PHASE3 PHASE4
Year 07 08 09 10 11 12 13 14 15 16 17 18 19 20 22 23 24 25 26
Coal SC Tokamak Operation Technology Steady-state Operation High-beta, AT Operation Sheady-state AT
Activities
  • First plasma
  • SC tokamak operation technology(Bt-3.5T)
  • D-shaped plasma(Ip>1MA,D2)
  • H-mode achievement
  • Collaboration for operation
  • Long pulse operation(tpulse>100s)
  • AT opertion Tech.(Pheat<20MW)
  • ITER pilot device operation
  • Collaboration for steady - state operation
  • Long pulse operation(tpulse>300s)
  • Sable AT operation(Pheat<20MW)
  • ITER satellite operation
  • Collaboration for advanced research
  • High beta AT mode & long pulse
  • Reactor meternal, test [divertor blanket]
Mileatone
  • 1st Plasma
  • 1MA
  • D-D Reaction
  • ITER Construction Start
100s
  • LonTemp>10kW
  • ITER 1st Plasma
 

KSTAR Operation Plan

Phase 1 (2008~2012)Obtain the baseline operation technologies for superconducting tokamak
  • Basic performance test of superconducting tokamak
  • Reproducing existing tokamak operation modes (including H-mode) in Short Pulse
  • Basic performance test of auxiliary systems for high performance, long pulse operation
Phase 2 (2013~2017)Develop long pulse plasma operation technologies
  • Long pulse operation of existing tokamak modes (up to 300seconds for H mode)
  • Realization of high performance AT mode under moderate power & magnetic field
  • Perform as an ITER Pilot Device
Phase 3 (2018~2022)Develop high performance, high efficiency AT mode technologies
  • Long pulse operation of AT mode under moderate heating power
  • Realization of high performance AT mode under high power & moderate magnetic field
  • Performance as an ITER Satellite Device
Phase 4 (2023~2025)Test of relavant prior arts for DEMO
  • Realization of long pulse operation for high power AT mode
  • Test of DEMO related prior arts

International Collaboration

KSTAR as an international research device with various collaboration programs

  • Technical development & training with advanced tokamak technology
  • World-wide fusion research center as an ITER piolt device
International Collaboration
KSTAR as an international research device with various collaboration programs
Technical development & training with advaced tokamak technology
World-wide fusion research center as an ITER pilot device
  • EU
    • IVCC techical design
    • D-T neutronics
    • NBI
    • Satety & risk managementfor ITER
    • Steady-state technology
    • PFC cooling
    • LHCD
    • Cryogenics
    • Divertor for steady-state operation
  • RUSSIA
    • SC coll design
    • SC tokamak commissioning
    • Hard X-ray diagn
    • Satety & risk managementfor ITER
    • Steady-state technology
    • PFC cooling
    • LHCD
    • Cryogenics
    • Divertor for steady-state operation
  • JAPAN
    • NBI development
    • Bolomety diagnostics
    • Thomsen laser system
    • ITER-like 170GHz gyrotron
    • Motor generator
    • ECH technology
    • Cryogenics
    • Diagnostics
  • USA
    • Plasma control system
    • ECCD launcher R&D. LHCD
    • AT-simulation. stability analysis
    • Visble fitterscope
    • Thomson, MSE/CER/BES R&D
    • High-speed plasma control
    • Control coil PS
    • Long-pulse ECH/ECCD.ICRH
    • Remote operation R&D
    • Integrated AT-mode simulation
    • Fusion Grid
    • NBI diagnostics(MES/CER/BES)
    • MIR/ECEI
    • Operation extent R&D
  • INDIA
    • Heating device
    • SC device operation
    • Diagnostics
  • CHINA
    • SC & control coll PS
    • SC device operation
    • Bilateral Workshop
  • KSTAR Progress
  • KSTAR Collaboration Interest

Commissioning Process

Commissioning Process
Commissioning Process
KEY DATES COMMISSIONING PROGRESS
  • Feb. 29, 2008
  • Apr. 03, 2008
  • Apr. 23, 2008
  • May. 12, 2008
  • May. 27, 2008
  • May. 29, 2008
  • Jun. 13, 2008
  • Jul. 15, 2008
  • Jul. 20, 2008
  • Aug. 02. 2008
  • Vacuum pumping stated after final inspection
  • Magnet system cool-down started(9 kW refrigerator)
  • SC phase transition detected (TF coil at 18 k)
  • TF coil commissioning completed (15 kA, 8 hr)
  • PF coil commissioning Completed (4 kA)
  • ECH pre-ionization test started (1.5 T, 84Ghz)
  • First plasma achieved (107 kA, ECH assisted)
  • 1st plasma campaing completed (pulse length up to 865 ms)
  • Warm up started
  • Completion of the 1st campaign
  • 2/29~8/7(Vacuum pumping system operation[161days])
  • 4/3~8/2(Cryo-facility operation[122days])
    • 4/3~4/26(Cool-down)
    • 7/20~8/2(Warm-up)
  • 4/26~7/20(Superconduction state[84days])
    • 4/26~5/29(Magnet test)
    • 7/15~8/2(Eng-test)
  • 5/29~7/15(Plasma operation [48 days])
    • 1st plasma
  • Maintenance & upgrade

1st plasma campagn result

  • Successfully operation of the superconducting tokamak in the first trial without any defect to prevent operation and plasma experiment
  • Successfully achievement of the 2nd harmonic ECH pre-ionization for the lower voltage plasma discharge
1st plasma campagn result
  • Left: Image of successful KSTAR first plasma generation.
  • Right: plasma performance (red - the maximum current value 133kA, pink - the retention time of up to 865ms, blue - the retention time of plasma high-current state, black - Plasma Goal)

Authorities concerned