JFT-2M Tokamak
(JAERI Fusion Torus-2M)
Device parameters |
major radius : 1.3 m
minor radius : 0.35 m
elongation : 1.7
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plasma volume : 4.8 m3
plasma current : 500 kA
toroidal field : 2.2 T
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Heating and current drive systems
Neutral beam injection heating : 1.6 MW, 40 keV
Electron cyclotron wave heating : 1.0 MW, 60 Ghz
Fast wave current drive : 0.8 MW, 200 Mhz
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We are challenging advanced subjects on fusion plasma research with flexibility of a medium-size device
- Current Research Subjects -
For the development of high performance plasmas and contribution to ITER physics R&D, following subjects are currently pursued.
- Advanced material tokamak experiments (AMTEX)
- Confinement and electric field
- Compact toroid injection
- Radio-frequency current drive & heating (ECW, FW)
- Divertor and boundary plasmas
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We have intensive collaborations with domestic and foreign universities and institutes.
Domestic
- Compact toroid injection
Himeji Insti. of Technology NIFS
- High confinement physics
NIFS, Tokyo Univ.
Yokohama National Univ.
- Current profile control by FWCD
Tokyo Univ.
- Excitation of shear Alfvén wave
Ibaraki Univ.
- Vacuum tech. of low-activ.-materi.
Hokkaido Univ.
- Development of membrane pump
NIFS
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International
- FWCD with combline antenna
General Atomics (USA)
- ECH
General Atomics (USA)
- Vanadium alloy exposure test
General Atomics/MIT (USA)
- Lost ion probe
Princeton University (USA)
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