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

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)