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Journal Articles

Overview of goals and performance of ITER and strategy for plasma-wall interaction investigation

Shimada, Michiya; Costley, A. E.*; Federici, G.*; Ioki, Kimihiro*; Kukushkin, A. S.*; Mukhovatov, V.*; Polevoi, A. R.*; Sugihara, Masayoshi

Journal of Nuclear Materials, 337-339, p.808 - 815, 2005/03

 Times Cited Count:56 Percentile:96.16(Materials Science, Multidisciplinary)

ITER is an experimental fusion reactor for investigation and demonstration of burning plasmas, characterised of its heating dominated by alpha-particle heating. ITER is a major step from present devices and an indispensable step for fusion reactor development. ITER's success largely depends on the control of plasma-wall interactions(PWI), with power and particle fluxes and time scales one or two orders of magnitude larger than in present devices. The strategy for control of PWI includes the semi-closed divertor, strong fuelling and pumping, disruption and ELM control, replaceable plasma-facing materials and stepwise operation.

Journal Articles

Numerical analyses of plasma and neutral particle behavior and design criteria for poloidal divertor in fusion experimental reactor

; ; *; *

Journal of Nuclear Materials, 128-129, p.114 - 117, 1984/00

 Times Cited Count:20 Percentile:86.58(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

A Review on Development of He Evacuation Systems for Tokamak Reactors

*; ; Murakami, Yoshio

JAERI-M 82-037, 48 Pages, 1982/04

JAERI-M-82-037.pdf:1.17MB

no abstracts in English

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