Abstract
The main design studies of the next fusion machines in Japan are divided into two categories: studies for a large device succeeding JT-60 supported by JAERI, and basic studies on a burning plasma and a steady-state toroidal plasma supported by the Japanese University Linkage Organization. The former corresponds to FER (Fusion Experimental Reactor), which is a long-pulse, burning machine to demonstrate engineering feasibility, and the latter includes the design study of the R-tokamak which had been done to prepare a rigid data base for introducing DT fuels producing in IPP Nagoya, and the conceptual design of a medium size helical system to achieve steady-state operation. Here plasma-surface interaction aspects of these design studies are reviewed.
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