Self-pumping impurity by in-situ metal deposition

Conference · Fri Jul 01 00:00:00 EDT 1983

OSTI ID:5588459

Brooks, J N; Mattas, R F

A system for in-situ removal of helium trapping in freshly deposited metal surface layers of a limiter or divertor has been studied. The system would trap helium on a limiter front surface, or a divertor plate, at low plasma edge temperatures, or in a limiter slot region, at high edge temperatures. Fresh material, introduced to the plasma and/or scrape-off zone, would be added at a rate of about five times the alpha production rate. The material would be reprocessed periodically, e.g. once a year. Possible materials are nickel, vanadium, niobium, and tantalum. Advantages of a self-pumping system are the absence of vacuum ducts and pumps, and the minimization of tritium processing and inventory.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5588459
• Report Number(s): CONF-830795-3; ON: DE83017937
• Resource Relation: Conference: Symposium on energy removal and particle control and toroidal fusion devices, Princeton, NJ, USA, 26 Jul 1983
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
HELIUM
GETTERING
REMOVAL
IMPURITIES
COATINGS
DIVERTORS
LIMITERS
NICKEL
NIOBIUM
TANTALUM
TRAPPING
VANADIUM
ELEMENTS
FLUIDS
GASES
METALS
NONMETALS
RARE GASES
TRANSITION ELEMENTS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing