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Charles C. Baker

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ITER Technology R&D, Fusion Engineering and Design, Vol.55, July 2001 ... 1. Massive Gas Puff for Disruption Mitigation - Mainline Tokamaks ... – PowerPoint PPT presentation

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Title: Charles C. Baker


1
U.S. Technology Interests in ITER
Charles C. Baker Deputy US ITER Planning
Officer presented at the Fusion Power
Associates Annual Meeting and Symposium Washington
, DC 19-21 November, 2003
Principal Information Sources - www.iter.org -
ITER Technology RD, Fusion Engineering and
Design, Vol.55, July 2001 - Summary of the ITER
Final Design Report, July 2001
2
R. Aymar/ Fusion Engineering and Design 55 (2001)
Fig. 1 Cutaway of ITER
3
T. Mizoguchi/Fusion Engineering and Design 55
(2001)
Fig. 1 Central solenoid model coil (CSMC)
configuration (above) and fabricated modules
(below) during assembly at JAERI, Naka (JA).
Another TF insert coil is fabricated by Russia
and tested at JAERI.
4
H. Tsuji et al. /Fusion Engineering and Design 55
(2001)
Fig. 2 Fabrication flow of CS model coil and CS
insert coil.
5
T. Mizoguchi/Fusion Engineering and Design 55
(2001)
Fig. 10 Integrated inner divertor cassette
(above left) at Sandia (US), integrated outer
divertor cassette (below) at EFET (EU) and high
heat flux testing of divertor target by ion beam
(above right) at JAERI, Naka (JA).
6
T. Mizoguchi/Fusion Engineering and Design 55
(2001)
Fig. 6 Demonstration of remote welding (US).
7
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8
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9
RF Technology Highlight The JET-EP ICRF Antenna
and the High Power Prototype (HPP)
10
ECH Highlight 1.5 MW, 110 GHz Gyrotron
Development
11
Plasma Fueling Highlights 1. Massive Gas Puff
for Disruption Mitigation - Mainline Tokamaks 2.
Pellet injector in a Suitcase - Alternative
Confinement Devices 3. Pellet fuelling - H-mode
fuelling
12
ITER provides Unique Technical Challenges for
Diagnostics
Measurement requirements demand performance
capability for present-day machines
alpha-particle measurement, operation in
radiation environment, presence of blankets,
reliability, calibration maintenance, control
data for machine protection. Significant
engineering design issues.
Port-plug with penetrations for Thomson
scattering, interferometry, etc.
  • 2m high x 1.8m wide x 3.5m long
  • Weight 66 tonne
  • Side and bottom 130mm thick
  • Front port flange 200mm

Designs by C. Walker (JCT)
Equatorial port-plug concept
13
Construction Schedule
  • 7 year construction
  • 1 year integrated commissioning
  • ITER Legal Entity established about2 years
    before award of construction license
  • Long lead item calls for tender sent out and
    procurement started before license awarded
  • Success-oriented schedule First plasma in 2013
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