DocumentCode :
2038877
Title :
Graphite as a plasma-facing material in fusion experiments
Author :
Langley, R.A.
Author_Institution :
Oak Ridge Nat. Lab., TN, USA
fYear :
1989
fDate :
2-6 Oct 1989
Firstpage :
522
Abstract :
The four major processes involved in hydrogen retention in graphite are reviewed. These processes are saturation of the near-surface region, diffusion on surface-connected porosity, intragranular diffusion, and erosion of carbon with concomitant formation of codeposited hydrogen-carbon films. It is suggested that in the retention of tritium in a fusion experiment the fourth process will dominate; therefore, from that point of view, it is the most important. To address the question of plasma fuel purity, more data are needed on ion-induced release of hydrogen isotopes by hydrogen isotopes and by heavier ions (e.g. carbon and oxygen) as a function of temperature
Keywords :
fusion reactor materials; graphite; C; fusion experiment; graphite; intragranular diffusion; ion-induced release; near-surface region; plasma fuel purity; surface-connected porosity; Anisotropic magnetoresistance; Gases; Heat pumps; Hydrogen; Magnetic materials; Plasma devices; Plasma materials processing; Plasma properties; Plasma temperature; Thermal resistance;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
Type :
conf
DOI :
10.1109/FUSION.1989.102274
Filename :
102274
Link To Document :
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