Present State and Future Plan for Chinese Magnetic Fusion Research Jiangang LI for EAST team and all

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Present State and Future Plan for Chinese
Magnetic Fusion Research Jiangang LI for EAST
team and all collaborators1. Institute of
Plasma Physics, Chinese Academy of Sciences,
Hefei, China2. Donghua University, Shanghai,
China3. South West Institute of Physics, Chengdu
China4. Tsinghua University, Beijing, China 5.
University of Science and Technology of China,
Hefei, China6) General Atomic, San Diego, USA7)
Fusion Research Center, UT at Austin, USA8)
Princeton Plasma Physics Laboratory, USA9) Tri
Alpha Energy, California, USA 10) National
Institute for Fusion Sciences, Toki, Japan11)
Association Euratom-CEA, CEA Cadarache,
France12) Natiaon Fusion Research Institute,
Daejeon, Korea 13) ORNL, USA
EAST
ASIPP
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EAST
Outline
Present state of EAST EAST Research Plan in next
2-5 years Future Plan of CN-MCF program Summary
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PFC strategy for EAST
EAST
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Key elements in-vessel
Internal Cryo-Pump

• Actively-cooled PFC
• (9000 tiles)
• Internal Cryo-Pump
• LHCD 2.45GHz, 2MW
• ICRF 30-110MHz,1.5MW
• Magnetic sensors
• 2 Removable limiter

ICRH antenna
Removable Limiter
75,600L/S for D2 107,000L/S for H2
LHCD antenna
High heat flux region 2MW/m2
Total 37 flux loop
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EAST Diagnostics

• Diagnostics in initial two campaigns, total 20
• ----Machine protection and plasma control,
  description of the basic
• plasma performance with SS wall, H
• 5 new constructed, 15 moved from
  HT-7 with minor modification
• Diagnostics in 3rd campaign, total 25
• ----Same function above with graphite tile
  wall, D
• 8 new constructed, 10 modified for
  DN plasma configuration
• Diagnostics from 4th campaign, total 30
• ----Evaluation and optimization of the
  plasma performance
• ----Focusing on key profile parameters

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PSI RF Conditionning
EAST
ASIPP

• ICR conditioning were successfully carried out in
  EAST, a divertor SC tokamak with metal/C walls.
• ICR cleaning, recycling control, boronization and
  oxidation have been carried out and compared with
  GDC.
• High pressure and RF power are favorable for
  removal of hydrogen and impurities.
• Wider operation widows (EAST 5-30kW, 10-4-10Pa
• HT-7 10-60kW, 10-4-10-2Pa) and higher
  removing rate were obtained.
• RF-Boronization has been routinely used for all
  campaions with about 200nm thinkness. 30-60 min.
  He RF conditioning was used for control
  recycling. Very good plasma performance can been
  easily obtained.
• RF-Li coating has been carried out. Higher plasma
  parameters and lower recycling were obtained.

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Divertor Physics Experiments

• Assessment of basic divertor plasma behavior
• Effect of divertor configurations Comparison
  between single null and double null
• Divertor asymmetry and drift effects Comparison
  between normal and revered toroidal fields
• Effect of gas puff locations on divertor
  asymmetry and fuelling efficiency
• Divertor screening for intrinsic carbon by CH4
  puffing
• Active control of divertor heat flux by Ar
  puffing
• Effect of divertor cryopump

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Full LHCD experiments

• Fully non-inductive discharge has been achieved
  both in DN and SN configuration.
• Higher injected LHW power results lower li,
  meaning off-axis CD.
• Power deposition peaked at rho0.5
• The electron temperature profile was not
  significantly changed

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Long Pulse Discharges
In 2008
In 2009

• Improved LHCD system, particularly control of
  power supply
• Optimized LHW coupling under reliable plasma
  shape control based on EFIT/Iosflux control
  algorithm
• Higher fuelling efficiency from Dome (see
  divertor experiments) reduced the fuelling gas
  amount for same line averaged density, e.g.
  retention of gas

13865.aviSee video
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EAST 2010 capabilities
PF power supply upgrade VDI stablizer
connection PFC modification for 2500C and longer
pulse with different puffing (place and gases)
For 1MA operation
H-mode operation
For ITER Safe start-up termination VDI PWI Fueli
ng Wall conditioning

• 2(4)MW LHCD _at_ 2.45GHz ?
• 1.5MW ICRF _at_ 30-110MHz ?
• 4.5MW ICRF _at_ 25-75MHz ?

• Diagnostics(2010)? all key profiles and some of
  specific measurements for physics understanding

Start ECRH program
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EAST near future Plan
EAST
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Try to Build a Close Coupling between Theory and
Experiments
EAST
CAS-MCF-theory center
MHD EqulibruimPCS Stability EFIT, EQ, TOQ
GATO
Heating Current drive CURRAY TORAY TORIC LHSTAR
Divertor, SOL,
Plasma wall interaction
Heatparticle removal
SOLPS(B2/Eirene), Bout
DEGAS2,Ero
Integration Transport turbulence ONETWO
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New wall Conditioning techniques
EAST
ASIPP

• ICR conditioning has been successfully carried
  out in EAST
• recycling control, boronization, Li coating and
  oxidation in comparison with GDC.
• High pressure and RF power are favorable for
  removal of hydrogen and impurities.
• HF GDC conditioning was tested with very simple
  arrangement
• Both are promising for ITER

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New Method HF_GD
Anode for HF_GD
Vacuum System for Table Testing

• Power SupplyU1.0KV,f100KHz,I0.5-1.0A
• Work GasAr,He,H2.
• Anode Plate
• Vacuum SystemØ400x600,V40l
• Gas-puffing ValveVDE016,GaugePKR251
• To explore the characters of HF_GDC breakdown

HF_DC Power Supply
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In EAST HF_GD Vs Pressure
P1.0Pa_at_ Bt1.5T
P5.0Pa_at_ Bt1.5T
In the same toroidal field, high-frequency glow
in the current power supply capacity related to
the pressure range of P 5.0E-1Pa-5.0Pa.
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In HT-7 Bt0, P8.0E-2Pa, IGD1.0A
Horizontal view window _at_Mid-plane
Vertical view window _at_Top
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The probe floating potential
With Bt1.0T
Without Bt
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PSI in ASIPP
EAST

• PFC strategy for EAST
• SiC/C tiles bolting to heat sink
• W/Cu-PFMC project
• VPS-W coatings
• Testing of W/Cu-PFC
• Plasma exposure on tokamaks
• Plasma/ion beam exposure at laboratories
• Studies on Plasma-Wall Interactions
• Wall Conditioning
• Fueling, retention, erosionredeposition
• Future Plan

Provide a valuable information for ITER
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PFMC Plan for EAST

• Plasma-facing Materials and Components (PFMC)
• Initial phase (2006-2007)
• PFM ? SS plates bolted directly to the support
  without active cooling
• First phase (2008-2011)
• PFM ? SiC-coated doped graphite tiles bolted to
  Cu heat sink cooled actively, max. heat flux
  capability lt2MW/m2,Li wall in HT-7
• Second phase (2012-2016)
• PFC ? Actively-cooled W/Cu and partial W/Fe
  possibly, max. heat flux capability of 710MW/m2
• Actively-cooled W/Cu divertor project launched
  recently at ASIPP
• Li wall in EAST

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2009-10-28
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Providing Experiences for ITER Main PSI Issues
EAST
ASIPP

• Full C PFC (-2010) 2 MW/m2, 350 ?C
• W/Cu divertor(-2014) 400 ?C, 10 MW/m2,
  liquid LI divertor
• Full W PFC (-2016), gt 500 ?C
• RF wall conditioning techniques in divertor
  devices (cleaning, isotopic control,
  boronization).
• Develop Tritium removal techniques that could be
  applicable to ITER.
• Steady-state erosion, redeposition and dust
  formation.
• In-situ control of T-codeposition and inventory
  by surface temperature control.

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Providing Experiences for ITERAT SSO Issue
EAST
ASIPP

• Technologies for SS HCD (LHCD, RF, NBI, ECRF)
• Coupling to the AT high performance plasma.
• Extend pulse length to steady-state condition
  with fully non-inductive current drive (LHCD
  Bootstrap).
• SS ELMy control and mitigation

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3 Tokamaks in universityFor education
There are 30 stuff 40 students for tokamak
experiments. Theory group 1010 Material
1010 Others2020
KT-5 in USTC
J-TEXT in Huazhong Univ.
SUNIST in Tshinghua
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HL-2A tokamak-present status
Status of HL-2A
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SWIP
HL-2A
ELM H-mode on HL-2A
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Physics of energetic particles
Toroidalcity induced Alfvén eigenmode (TAE)
during NBI
E-fishbone on HL-2A during ECRH
n1, m2m3 coupling
TAE
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HT-7 experiments
ASIPP
HT-7
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HT-7
ASIPP
Repeatable 400s discharges (Te01.0keV)
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CN-ITER Home Teams
ASIPP

• Join the negotiation from 2003.2
• ITER-CN national committee
• Join ITER and ITPA activities
• CN-ITER home team ( Hefei-Chendu branches) has
  been established.
• CN-Package Feeders, Correction coils, Magnetic
  supports, PF conductor, Blanket, Transfer cask,
  AC-DC converter, Diagnostics, GDC and fueling, TBM

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ITER-RD
CICC conductor
SC magnets
VPI
machining
RD for ITERrelated technologies
Power supply
SC magnet testing
Cryogenic
HTc feeder
Plasma control
PFC
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ITER-Conductor
Multi-Vender activities
Central tube Tai Steel,
Wire NICNC,Oxford
CoatingShenghai Ltd
Wire testingASIPP
Cabling Basheng Ltd,
316LN Tube
IntegrationASIPP
1000m jacketing line In ASIPP
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ITER
ASIPP
RD of TBM
Dual-cooled He/LiPb (DLL) TBM

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Feeder
TF feeder9
PF feeder6
CS feeder6
CS/TF joint feeder3
CC feeder5
Diagnostic feeder2
Total31 different feeders
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Detail design is nearly finished
CTB
DB
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ITER
HTc current leads

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Near term CN-MCF Plan (2020)

• ITER construction
• ASIPP Feeders (100), Correction Coils (100),
  TF Conductors (7) , PF Conductors (69),
  Transfer Cask System(50), HV Substation
  Materials (100), AC-DC Converter (62)
• SWIP Blanket FW (10) Shield (40), Gas
  Injection Valve Boxes GDC Conditioning System
  (88), Magnetic Supports (100),
• Diagnostics (3.3)

• Enhance domestic MCF
• Upgrade EAST, HL-2M
• ITER technology
• TBM
• University program
• DEMO design
• Material

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Further Opportunities

• ASIPP aims to establish a long lasting
  collaboration
• possibility of doing experiments from US once
  collaboration is established
• Our research program will be put in our web
  before the end of each year. Proposals are
  welcomed and reviewed.
• We have excellent students (USTC,others)

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Education of young generation
EAST
ASIPP

• There are nearly 140 young stuff scientists and
  250 students who are under 35 years old.
• We are lack of experienced advisers.
• We are going to send many good young persons to
  foreign labs for further education.
• Establish a international advisory group for
  training students via internet.
• Assign good and interesting topics to young stuff
  and students.

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Summary
ASIPP

• With HL-2A, HT-7 and EAST operation, China will
  make more efforts for fusion development.
• With ITER project, China will work more closely
  with other 6 parties for fusion research.
• More close cooperation between China and USA will
  beneficial fusion research.
• ASIPP would like to have close cooperation with
  PPPL for the early use of fusion energy.

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EAST
ASIPP
Thanks
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