ELECTRON beams, ION sources, STELLARATORS, PLASMA devices, ELECTRON accelerators
Abstract
This paper reviews the operational phase of the negative-ion-based neutral beam systems on the JT-60U tokamak in Naka, Japan and the large helical device (LHD) stellarator in Toki, Japan. These systems were the first high power negative ion beam systems to be deployed for any application, and thus represented large advances in the state of the art for negative ion sources and accelerators, especially since the ions used were hydrogen and deuterium, which have only a modest electron affinity. This paper re- views the systems, the principal problems encountered, and the improvements they engendered, as well as the progress of these systems to the present time. The role of neutral beams in fusion is also discussed, and some of the contributions of the negative ion systems to the physics programs of JT-60U and LHD are briefly reviewed. These systems have been central to the success of JT-60U and LHD, and the knowledge gained about their characteristics should provide a strong basis for the development of the next generation of negative-ion-based neutral beams for ITER and other large fusion devices. [ABSTRACT FROM AUTHOR]
CONFERENCES & conventions, ELECTRIC insulators & insulation, MICROELECTRONICS, VACUUM, ASSOCIATIONS, institutions, etc.
Abstract
Information about the twenty-second International Insulation in International Symposium on Discharge and Electrical Insulation in Vacuum (ISDEIV) which was held in Marsue, Japan on September 25-29, 2006 is presented. The symposium was hosted by the Vacuum Society of Japan. The conference was significantly altered to include developing vacuum microelectronics devices, surface modification technologies and other new vacuum plasma applications.
DIRECT currents, TOKAMAKS, HYBRID integrated circuits, CONCEPTUAL design, ELECTRIC potential
Abstract
This paper describes the detailed design of the quench protection circuits (QPCs) for the superconducting toroidal field (TF) and poloidal field (PF) magnets of the satellite tokamak JT-60SA, which will be installed in Naka, Japan. The nominal currents to be interrupted and the maximum reapplied voltages are 25.7 kA and 2.8 kV for the TF QPCs and 20 kA and 5 kV for the PF QPCs. The innovative solution proposed in the QPC design is based on a hybrid circuit breaker (CB) composed of a mechanical bypass switch for conducting the continuous current, in parallel to a static CB for current interruption. The main choices of the final design are presented and discussed, either to confirm or to update and complete the study performed at the conceptual design level. [ABSTRACT FROM PUBLISHER]