DocumentCode
324979
Title
ITER tokamak dust-limits, production, removal, surveying
Author
Piet, S.J. ; Costley, A. ; Federici, G. ; Heckendorn, F. ; Little, R.
Author_Institution
Nat. Eng. & Environ. Lab., Idaho Falls, ID, USA
Volume
1
fYear
1997
fDate
6-10 Oct 1997
Firstpage
167
Abstract
Some tokamak dust will exist inside the ITER Vacuum Vessel as a result of routine sputtering, disruptions, and possibly maintenance related activities. The three plasma-facing materials (beryllium, carbon, tungsten) will give rise to a dust mixture with radiological, chemically toxic, and chemically reactive hazards. The project has evolved an approach to ensuring that the public is protected via confinement, limiting chemical reactions, and limiting the dust inventory. This paper provides an overview of the dust safety limits, production, removal, and surveying methods
Keywords
beryllium; carbon; dust; fusion reactor safety; tungsten; Be; C; ITER; Vacuum Vessel; W; chemical reactions; dust; dust inventory; dust removal; plasma-facing materials; safety; surveying; Chemical hazards; Dusty plasma; Hazardous materials; Plasma chemistry; Plasma confinement; Plasma materials processing; Production; Sputtering; Tokamaks; Toxic chemicals;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687012
Filename
687012
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