Divertor target for magnetic containment device

Patent · Tue Aug 10 00:00:00 EDT 1982

OSTI ID:6614314

Luzzi, T E

In a plasma containment device of a type having superconducting field coils for magnetically shaping the plasma into approximately the form of a torus, an improved divertor target for removing impurities from a ''scrape off'' region of the plasma comprises an array of water cooled swirl tubes onto which the scrape off flux is impinged. Impurities reflected from the divertor target are removed from the target region by a conventional vacuum getter system. The swirl tubes are oriented and spaced apart within the divertor region relative to the incident angle of the scrape off flux to cause only one side of each tube to be exposed to the flux to increase the burnout rating of the target. The divertor target plane is oriented relative to the plane of the path of the scrape off flux such that the maximum heat flux onto a swirl tube is less than the tube design flux. The containment device is used to contain the plasma of a tokamak fusion reactor and is applicable to other long pulse plasma containment systems.

• Assignee: Dept. of Energy
• Patent Number(s): US 4343760
• OSTI ID: 6614314
• Resource Relation: Patent File Date: Filed date 14 Nov 1979; Other Information: PAT-APPL-093952
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
TARGETS
DIVERTORS
TOKAMAK TYPE REACTORS
PLASMA CONFINEMENT
COOLANTS
GETTERING
MAGNETIC FLUX
MAGNETISM
SUPERCONDUCTING COILS
TOROIDAL CONFIGURATION
TUBES
VACUUM SYSTEMS
VORTEX FLOW
WATER
ANNULAR SPACE
CONFIGURATION
CONFINEMENT
FLUID FLOW
HYDROGEN COMPOUNDS
OXYGEN COMPOUNDS
SPACE
THERMONUCLEAR REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing