Fusion Science and Technology / Volume 52 / Number 3 / October 2007 / Pages 347-356
Technical Paper / The Technology of Fusion Energy - Overview / dx.doi.org/10.13182/FST07-A1513
For ITER, trial fabrications of a superconducting cable for a Toroidal Field coil conductor and jacket sections for a central solenoid conductor were successfully performed. In the radio-frequency heating technology, development of 170 GHz ITER gyrotron has progressed to achieve a 600 kW for 3600 sec operation in JAEA RF test stand. In LHD, long-pulse operations near 1 hour with 1.6 GJ inputs have been achieved with ICH and ECH, and subcooled operations of SC magnets to improve cryogenic stability are scheduled soon. In the ITER Test Blanket Modules project, Japan has a plan to lead a water cooled ceramic breeder blanket concept, and to cooperate with other parties on other blanket concepts, such as, a helium cooled ceramic breeder blanket, a LiPb blanket, a Li/V blanket, and a molten salt blanket. As the Broader Approach activities between Europe and Japan, ITER satellite tokamak, JT-60SA, IFMIF-EVEDA and the International Fusion Energy Research Center programs will start soon in Naka and Rokkasho, respectively. Basic researches on broad areas have been enhanced with collaborations in the Fusion Engineering Network among Japanese universities and research institutes.