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[en] A stabilized pinch configuration is described, consisting of a D-shaped plasma cross section wrapped tightly around a guiding axis. The open-quotes helical-Dclose quotes geometry produces a very large axial (toroidal) transform of magnetic line direction that reverses the pitch of the magnetic lines without the need of azimuthal (poloidal) plasma current. Thus, there is no need of a open-quotes dynamoclose quotes process and its associated fluctuations. The resulting configuration has the high magnetic shear and pitch reversal of the reversed field pinch (RFP). (Pitch = P = qR, where R = major radius). A helical-D pinch might demonstrate good confinement at q << 1
[en] SINP Tokamak was made operational in July, 1987. The power supply system of the tokamak at that time was designed for a plasma duration of around 2 ms for a peak plasma current of 75 kA. Efforts were directed to increase this duration to 20 ms with the help of a slow bank system designed to work in conjunction with the original fast bank system. The design aspects of the system were completed and the system has been partially executed. Subsequent to this partial implementation, efforts were directed to incorporate the necessary control system and interface facilities between the existing fast bank and the developed slow bank systems. The significant features of the control circuits are that they work according to a well thought out sequences of logic and are designed to guard against possible failures in the existing or the developed power supplies. Efforts have been put to make the operation of the system as much user-friendly as could be worked out within certain practical constraints. The control circuit and interface facilities have been put to extensive tests and are found to work satisfactorily. The entire power supply system is now in active use for different research programmes in the group. (author)
[en] Plasma displacement control plays an important role in the experiments on HL-1M. It is significant to study how to improve the operation condition, stability and reliability of the control system, and to satisfy the operation requirement of HL-1M, because the operation condition will directly affect the discharge quality and the final result of different experiment. The computer auto-feedback control system for plasma displacement control is presented. By using the computer and the high accurate electronic component the great amelioration has been made on plasma displacement control, discharge quality and efficiency
[en] The ITER management advisory committee meeting was held on 8 March in Cadarache, France. The main topics were the ITER EDA Status Report in the period between the ITER Meeting in Yokohama (October 1990) and February 1999. In particular, the management advisory committee shares the director's concern about the uncertainties against which the whole project operates at present. They also noted that the definition of an appropriate framework for continued US involvement in on-going projects is a very important issue
[en] The ITER Technical Advisory Committee meeting took place on 24-27 February at the Garching Joint Work Site. According to the discussions at the ITER meeting in Yokohama in October 1998, the Technical Advisory Committee was requested to conduct a thorough review of the document 'Options for the reduced technical objectives / reduced cost ITER'