Detailed Design Has Been Developed

1
Detailed Design Has Been Developed
Central Solenoid Nb3Sn, 6 modules
Blanket Module 440 modules
Port Plug heating/current drive test
blankets limiters/RH diagnostics
Poloidal Field Coil Nb-Ti, 6
Toroidal Field Coil Nb3Sn, 18, wedged

• Divertor
• 54 cassettes

Torus Cryopump 8 units
Fusion Power 500 MW Plasma Volume 840 m3 Plasma
Current 15 MA Typical Density 1020 m-3 Typical
Temperature 20 keV
Vacuum Vessel 9 sectors
Cryostat 24 m high x 28 m dia.
2

• Fusion Research During the ITER Era
• James Drake
• Head of the Swedish Fusion Research Unit
• Association EURATOM - VR

3
(No Transcript)
4
Following the site-decisioninnovative
arrangements are being sought

• Worldwide mega-project
• Management challenge and organization structure
  still under discussion
• Change of scale for fusion, needs
• Strong QA program
• Strong systems integration
• Fusion laboratories experience
• Strong industrial involvement
• The key organizational challenges for resolution
  are
• Management of a major international construction
  project
• Complex procurement policy
• Risks
• Staffing forging one coherent project team
  across multiple cultures
• Financial regulations
• Intellectual property
• ..

5
Urgent PWI RD for ITER

• The high priority issues for ITER that must be
  addressed in tokamak experiments or laboratory
  simulations aided by modelling are
• tritium co-deposition and effective control of
  inventory
• plasma operation with a beryllium first wall
• the use of tungsten as a plasma facing component
• the effects of material mixtures
• the mitigation/suppression of ELMs and
  disruptions
• The answers to these questions must be
  forthcoming in a time scale not exceeding the
  ?2010?.
• Main elements of a strategy in this directions
  are
• JET with a Be wall and W and/or C divertor
• ASDEX Upgrade (entire W device) C-Mod
• C deposition and removal (TEXTOR, Tore Supra,
  DIII-D)
• Work on ELMs/disruption damage on CFC W targets
  in Russian plasma guns
• Work on Be/C and Be/W mixed materials in PISCES-B.

(? Talk of A. Loarte)
6
Proposed participation in the JETcampaigns of
late 2005 / early 2006
Increased participation in the campaigns
involving 19 countries
7
RWM feedback control with the full 4x32 coil array

• September Data
• red Reference shot w/o fb black With
  intelligent shell feedback control
• Refined intelligent shell mode of operation.
• All unstable RWMs are suppressed (16 modes)
• The field error amplification (n2) is
  suppressed.
• Feedback results in a three-fold increase of the
  discharge duration
• Stabilization is achieved for 10 wall times

8
EXTRAP T2R Plans

• 100 ms pulse length (requirements)
• Rebuild VF power supply (underway).
• Use full capacitance of sustainment bank
  (commissioned).
• Density control by gas puff (already tested).
• Core bias to use full flux swing. (Installed but
  not commissioned)
• Test different sensor array configurations
• Use B-toroidal array.
• Aim is to reduce coupling between actuator array
  and sensor array.
• May need more signal processing.
• Is B-toroidal array as effective for FE
  compensation.
• Look for non linear effects.
• Apply pre-programmed harmonics and look for mode
  coupling.

9
EXTRAP T2R Plans

• Simulate a big port hole in the shell and correct
  with a combination of dedicated coils and
  harmonic control.
• QSH
• Is there a scenario where a large amplitude
  resonant mode can be produced and then dragged to
  start rotation leading to unlocking with reduced
  B-radial?
• PPCD
• A target plasma that has an intelligent shell and
  rotating inherant resonant modes.
• Edge plasma
• Continue Alfven Eigenmode studies
• Continue probe studies.