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2007-1016-KTSAR_Operation

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2007-1016-KTSAR_Operation Powered By Docstoc
					KSTAR Research Objects and
      Operation Plan

           presented by J.Y. Kim
     National Fusion Research Institute




              2007. 10. 16
           ASIPP, Hefei, China
 Research Objectives

 To extend present stability and performance boundaries of tokamak
   operation through active control of profiles and transport.


 To explore methods to achieve steady-state operation for tokamak
   fusion reactors using non-inductive current drive.


 To integrate the high performance and steady-state operation
   as a step toward an attractive tokamak fusion reactor.


          demonstrate high-beta steady-state AT operation
Target Operation Goal
Advanced Design Features

 High-performance AT mode research
- A wide range of target operation space
- Equilibrium flexibility
- High-beta ideal MHD stability
- Active control capability of resistive MHD modes
- Flexible heating & CD systems
- Advanced diagnostics & control systems

 Steady-state operation research
- Superconducting TF & PF magnet system
- Long-pulse heating & CD system
- Long-pulse divertor & PFC system
- Long-pulse diagnostics and control systems

 Integrated operation research of long-pulse AT mode
- Advanced real-time plasma control system
 Equilibrium Flexibility
 PF-coils dimension optimized to provide target equilibrium space
 against superconducting limit


     5                                                                    7

                     4              5                                     6
     4




                                                     Equilibrium Number
                                                                          5
     3         3
                                                                          4
N




     2
               2                                                          3
                                    6                                             PF5
     1
                                                                          2
                      1             7
     0                                                                    1

         0.4   0.6   0.8      1.0   1.2   1.4                                 0         2     4     6       8   10
                     l i(3)                                                             Flux Linkage (Wb)


         * Superconducting Allowables : Fraction of critical current (fc), Copper current
                 density (Jcu), Temperature margin (Tm), and Heat transfer coefficient (h)
High- Ideal MHD Stability


                                Strong Plasma Shaping
                                    (x  2.0, x  0.8)

                                 - high-n ideal ballooning stability
                                 - peeling-ballooning stability etc.

                                Conducting Passive Plate close to
                                 the plasma

                                 - low-n external kink stability

                                 - the slowing down of vertical
                                   position instability
Segmented In-Vessel Control Coil

                                                      Vertical Control




                                                                         Upper FEC/RWM
                                     Radial Control




                                                                   Middle FEC/RWM




                                     Radial Control                      Lower FEC/RWM




                                                      Vertical Control




  for multi-purpose control (position, field error, RWM, ELM, rotation etc.)
KSTAR Operation Strategy

 Phase-1      Initial Operation


           Steady-State Operation
 Phase-2                            ITER Pilot Device
                 Research


 Phase-3   High-Performance AT-
                                    ITER Satellite Device
              Mode Research


            Steady-State, High-
 Phase-4   Performance AT-mode      DEMO Pilot Device
                 Research
KSTAR Operation Plan
   년도         07     08      09     10   11   12     13   14     15      16   17   18    19    20      21    22   23   24       25


                             PHASE I                          PHASE II                  PHASE III                 PHASE IV


 Operation                                           Steady-state Operation              High beta, AT            Steady state
                          Initial Operation
   Goal                                                    Research                        Operation                  AT


                   • First Plasma                     • Long Pulse Operation        • Long Pulse Operation         • High beta
 Activities                                             (> 100 s)                     (> 300 s)                      AT mode &
                   • SC Tokamak Operation
                                                                                                                     long pulse
                     Technology (3.5 T)               • AT Operation                • AT Operation
                                                        Technology (< 20 MW)          Stabilization (> 20 MW)      • Material
                   • D-shaped Plasma (>1 MA)
                                                                                                                     Test for
                   • H-mode & D Plasma                • ITER Pilot Device           • ITER Satellite                 Reactor

                                                                          300 s
   Pulse                                              100 s
                                     20 s
                          0.5 s                                                                        > 300 s
  Length
                                     3.5 T
                          1.5 T
 TF Field                                                                                              > 3.5 T

                          0.5 MA     1 MA     2 MA
 Plasma
 Current                                                                                               > 2 MA


                          ECH                         LHCD
 Heating                             NBI-I                                                             > 28MW
                          ICRH
  Power                                                                  16MW
                                              6MW
Phase 1: Initial Operation (2008-2012)
- Commissioning and first-plasma generation
- Development of basic operation skill of superconducting tokamak
- Short-pulse standard operation mode experiments (Ohmic, L, H, Hybrid)
- Development of ancillary systems for long-pulse operation

               2007     2008     2009         2010            2011     2012
Operation              First-    Circular-   Shaped-Ohmic
                                                             H-mode    Hybrid-mode
Mode                   plasma    Ohmic          & L-mode
NBI (MW)                                      2.7                       2.7
ICRH (MW)       1.5
LHCD (MW)                                                      0.75
ECCD (MW)       0.5                           1.0                       1.0
Diagnostics    Basic   Base-I    Base-II     Base-III        Base-IV
                                             Position &
IVCC                                                         FEC       ELM
                                             Shape
                       Inner-                Divertor,
PFC
                       limiter               Passive-plate
Power supply           50 MVA                100MVA                    SN-PS
Experimental Operation Plan
Campaign-1   • First-Plasma Exp.
 (2008)      - ECH-assisted start-up (2nd harmonic)   ECH: 500kW, 84GHz
             - RF discharge cleaning                  IP ~ 100kA
Campaign-2   • Circular Ohmic-Plasma Exp.
 (2009)      - Plasma current ramp-up                 IP ~ 1 MA
             - ICRH heated plasma
Campaign-3   • Shaped Ohmic & L-mode Plasma Exp.
 (2010)      - D-shape plasma                         IP ~ 2 MA
             - Plasma position control by IVCC
             - ICRH & NBI heated plasma
Campaign-4   • H-mode Plasma Exp.
 (2011)      - L-H transition                         Ptot > 5MW
             - Field error correction by IVCC
Campaign-5   • Hybrid-mode Exp.
 (2012)      - q(0)>1 formation                       Ptot ~ 10MW
             - SN plasma experiment
Phase 2 : Long-pulse Operation (2013-2017)
- Increase of input power (>15MW) and pulse length (>300s)
- Basic physics study in long-pulse operation condition
- Real time MHD control (ELM, NTM etc.)
- Development of high-beta RS-mode in low input-power regime
                  2013        2014           2015        2016       2017
  Operation      Long-pulse   Long-pulse    RS-profile             High-beta
                                                         RS-mode
  Mode           H-mode       Hybrid        formation              RS-mode
  NBI (MW)                     2.0                                  2.0
  ICRH (MW)                    1.5
  LHCD (MW)      0.75                        1.5
  ECCD (MW)                    1.0                                  1.0
  Diagnostics    Upgrade for long-pulse operation
  IVCC                                                   RWM
  PFC            Upgrade for Long-pulse operation
  Power supply                                                     >100MVA
Experimental Operation Plan
              • Long-pulse H-mode Exp.                       < 100 sec
Campaign-6    - ELM control by IVC-coil
  (2013)      - HFS Pellet injection

Campaign-7    • Long-pulse Hybrid-mode Exp.
  (2014)      - q(0)>1 maintenance                           Full non-inductive
              - NTM stabilization (3/2 or 2/1)
Campaign-8    • Long-pulse H & Hybrid mode Exp.
  (2015)      - Radiative divertor                           PECCD : 3MW
              - NTM stabilization (3/2 & 2/1)
Campaign-9    • RS-mode Exp.
  (2016)      - RS profile formation                         PLHCD : 3MW
              - Off-axis LHCD and nearly-balanced NBI
Campaign-10   • High-beta AT-mode Exp. (in low power)
  (2017)      - Profile optimization of current & pressure   βN ∼ 4-5
              - RWM control by IVCC & rotation
Phase 3: High-beta AT Operation (2018-2022)
- Long-pulse operation of high-beta AT mode in low input-power regime
- Profile control of plasma current and pressure
- Integrated real-time MHD control (FEC, ELM. NTM, RWM etc.)
- AT-mode development In reactor-relevant condition
                  2018        2019         2020         2021          2022
  Operation      Long-pulse   Long-pulse   High-power   High-power
                                                                     High-beta AT
  Mode           AT-mode      AT-mode      AT-mode      AT-mode
  NBI (MW)        2.7          2.0
  ICRH (MW)                    1.5                       1.5
  LHCD (MW)
  ECCD (MW)                    1.0
  Diagnostics
                                           High-power
                 Long-pulse
  PFC                                      Long-pulse
                 tile
                                               tile
  Power supply
Experimental Research Plan
              • Long pulse AT-mode Exp. (low-power)
Campaign-11   - Increase of pulse length of high- AT mode       Pulse length ~ 100s
  (2018)      - Integrated control of FEC/ELM/NTM/RWM

Campaign-12   • Long pulse AT-mode Exp. (low-power)
  (2019)      - Real-time control of plasma profile              Pulse length ~ 300s
              - Demonstration of high- , steady-state AT mode
                operation in low input-power regime
Campaign-13   • AT-mode Exp. (high-power)
  (2020)      - Increase of input-power                          P : 16 -> 28MW
              - Increase of toroidal field and plasma current    B : 3 – 3.5T
Campaign-14   • AT-mode Exp. (high-power)
  (2021)      - Plasma Bootstrap current fraction increase       Te ~ Ti & low-rotation)
              - Experiment in reactor-relevant condition
Campaign-15   • High-beta AT-mode Exp. (high power)
  (2022)      - Pressure profile control                         βN > 4, fBS∼0.8
              - Bootstrap current fraction optimization
Phase 4: High-beta Steady-state Operation (2023-2025)

 - Demonstration of high-beta steady-state AT operation in high power
 - Provide a design basis for advanced DEMO operation scenario
 - Utilization KSTAR as DEMO pilot-device

 Campaign-16   • Long-pulse AT-mode Exp. (high-power)
   (2023)      - Beta and Bootstrap current fraction increase

 Campaign-17   • High-beta, steady-state AT-mode Exp.
   (2024)      - Demonstration of long-pulse operation of          βN ∼ 5, fBS∼0.9
                 high-beta AT mode in high input-power egime
 Campaign-18   • DEMO Pilot-plant Exp.
   (2025)      - Test of physics and engineering issues in DAMO-
                 relevant high heat-flux condition
               - PFC material, divertor, Blanket etc.
ITER-relevant Issues, which can be studied in KSTAR

 • Production and research of the ITER-like operation scenarios in long pulse (~ 300 s) an
   and high-performance operation condition

 • Investigation of the SC coil characteristics in high performance long pulse such as AC
   loss, magnetic forces, and etc.

 • Plasma heating system operational features with similar specification as ITER
  - Long-pulse NBI system operation
  - 2nd harmonic ECH startup
  - 170 GHz ECCD with same frequency as ITER
  - 5 GHz LHCD with same frequency as ITER

 • Real time plasma control and stabilization using active IVCC and ECCD control

 • Material test with high temperature divertor and magnetic blanket components

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

 KSTAR research objectives are
 - to demonstrate the steady-state operation of high-performance AT mode
   in support of ITER operation and advanced DEMO design

 To achieve this goal, KSTAR is now planned to operate over four phases,
  - Initial baseline operation
  - Steady-state operation
  - High-performance AT operation
  - Integrated operation of steady-state, high-performance AT mode

 A more detailed operation plan is under development for each phase

 There are many ITER-relevant research issues, which can be studied
  using KSTAR, so KSTAR may be utilized as an ITER pilot machine

				
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