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Presentations
Figures of JT-60/JT-60SA
*Click figures to enlarge.
  JT-60

JT-60 Tokamak Device
Progress of High Temperature Plasma Confinement in Tokamak


Progress of Fusion Plasma Performance
Engineering R&D for ITER Construction
ITER relevant plasmas have been sustained for 28sec with ferritic steel installation for field ripple reduction


R&D on steady state high β plasmas in JT-60
National research collaboration using JT-60


JT-60 remote experiment has been demonstrated with high security
JAEA contributions to IAEA fusion energy conference


Broader Approach: Satellite Tokamak Project (JT-60 Modification)
with utilization of existing JT-60 facilities
International Cooperation in Fusion Plasma Research

  JT-60SA

JA & EU Broader Approach Satellite Tokamak and National Centralized tokamak
Sharing of Construction of JT-60SA between JA and EU


JT-60SA is optimized for contribution to ITER
JT-60SA has various features to supplement ITER for DEMO


Basic Machine Parameter of JT-60SA
Toroidal Field Coil


Poloidal Field Coil
Vacuum Vessel, In-vessel Components


Cryostat