Progress of boundary plasma investigation toward ITER

Shimada, Michiya

Discussion is made on objectives of edge plasma and plasma-wall interaction studies, divertor performance projection of ITER and key R&D issues on plasma-wall interaction including material issues, tritium retention, and transient events like ELMs and disruptions. A perspective of future development is discussed for the purpose of projection to and control of ITER plasma.

Language	:	Japanese
Journal	:	Purazuma, Kaku Yugo Gakkai-Shi
Volume	:	80
Number	:	3
Pages	:	p.222 - 226
Publication Year/Month	:	2004/03
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Paper URL	:	https://doi.org/10.1585/jspf.80.222
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Keywords	:	ITER; Boundary Plasma; Power Control; Particle Control; Impurity Control; Plasma-facing Components
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Registration No. : A20030615
JAEA Abstracts No. : 320646
Paper Submission No. : 21085

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