ITER tokamak dust-limits, production, removal, surveying

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...

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Bibliographische Detailangaben
Hauptverfasser: Piet, S.J., Costley, A., Federici, G., Heckendorn, F., Little, R.
Format: Tagungsbericht
Sprache:eng
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Beschreibung
Zusammenfassung: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.
DOI:10.1109/FUSION.1997.687012