Glow-discharge removal of codeposited carbon films in graphite-lined tokamak reactors
In a graphite-lined tokamak reactor, the interaction of the plasma with the graphite first wall will result in the formation of carbon deposits that are highly rich in tritium. This mechanism of tritium retention will be a major contributor to the in-vessel tritium inventory. In this paper, the glow-discharge technique is proposed for removing these films to reduce the inventory buildup. Glow-discharge runs were performed with feed gases of H/sub 2/, He, N/sub 2/, and O/sub 2/. The results show that only oxygen glow discharges can remove carbon films at sufficiently large rates. The impact of this study on the Tokamak Fusion Test Reactor (TFTR) and the Compact Ignition Tokamak (CIT) is discussed. A recipe for effective glow-discharge operation on TFTR and CIT is also described.
- Research Organization:
- Sandia National Laboratories, Livermore, California 94550
- OSTI ID:
- 6265884
- Journal Information:
- J. Vac. Sci. Technol., A; (United States), Journal Name: J. Vac. Sci. Technol., A; (United States) Vol. 7:3; ISSN JVTAD
- Country of Publication:
- United States
- Language:
- English
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Tritium retention and removal on TFTR
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Related Subjects
700201* -- Fusion Power Plant Technology-- Blanket Engineering
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CARBON
CLEANING
CLOSED PLASMA DEVICES
ELECTRIC DISCHARGES
ELEMENTS
FILMS
FIRST WALL
GLOW DISCHARGES
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NONMETALS
NUCLEI
ODD-EVEN NUCLEI
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RADIOISOTOPES
SURFACE CLEANING
SURFACE FINISHING
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
TRITIUM
YEARS LIVING RADIOISOTOPES