Development and Operational Experiences of the JT-60U Tokamak and Power Supplies

Journal Article · Sun Sep 15 04:00:00 EDT 2002 · Fusion Science and Technology

OSTI ID:20845858

Hosogane, N ^[1]; Ninomiya, H ^[1]; Matsukawa, M ^[1]; Ando, T ^[1]; Neyatani, Y ^[1]; Horiike, H ^[2]; Sakurai, S ^[1]; Masaki, K ^[1]; Yamamoto, M ^[1]; Kodama, K ^[1]; Sasajima, T ^[1]; Terakado, T ^[1]; Ohmori, S ^[1]; Ohmori, Y ^[1]; Okano, J ^[1]

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1. Japan Atomic Energy Research Institute (Japan)
2. Osaka University (Japan)

The design of the JT-60U tokamak, the configuration of the coil power supplies, and the operational experiences gained to date are reviewed. JT-60U is a large tokamak upgraded from the original JT-60 in order to obtain high plasma current, large plasma volume, and highly elongated divertor configurations. All components inside the toroidal magnetic field coils, such as vacuum vessel, poloidal magnetic field coils, divertor, etc., were modified. Various technologies and ideas were introduced to develop these components; for example, a multi-arc double skin wall structure for the vacuum vessel and a functional poloidal magnetic field coil system with taps for obtaining various plasma configurations. Furthermore, boron-carbide coated carbon fiber composite (CFC) tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semiclosed divertor with pumps, for which cryo-panels originally used for NBI units were converted, was installed in the replacement of the open divertor. These development and operational results provide data for future tokamaks. Major failures experienced in the long operational period of JT-60U, such as water leakage from the toroidal magnetic field coil, fracture of carbon tiles, and breakdown of a filter capacitor, are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers is described.

• OSTI ID: 20845858
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 2,3 Vol. 42; ISSN 1536-1055
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BORON CARBIDES
CARBON
CONTAINERS
DESIGN
DEUTERIUM
DIVERTORS
ELECTRIC CURRENTS
EROSION
JT-60 TOKAMAK
JT-60U TOKAMAK
MAGNETIC FIELD CONFIGURATIONS
MAGNETIC FIELDS
MAINTENANCE
PLASMA
POWER SUPPLIES