- Introduction of JFT-2M
- JFT-2M Tokamak
- Panorama of the Device
- Main Performance
- Current Research Subjects
- Collaborations
- Advanced material tokamak experiment program
- Development of new fuelling method
- Compact toroid injection: collaboration with HIT - - Study of improved confinement
- Heavy ion beam probe: collaboration with NIFS - - Study of closed divertor
- Disruption control study with ECH/ECCD
- Fast wave current drive study
JFT-2M Tokamak (JAERI Fusion Torus-2M)
Main Performance
Device parameters
major radius : 1.3 m
minor radius : 0.35 m
elongation : 1.7
plasma volume : 4.8 m3
plasma current : 500 kA
toroidal field : 2.2 T
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
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
Collaborations
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
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)