Patent Number: 053533143
Section: claims

1. An electric field plasma pump for use within a plasma-confining apparatus, said plasma-confining apparatus including a vacuum vessel having electrically conductive walls, and having means for generating magnetic fields B to confine a plasma to the interior of said vacuum vessel, said plasma-confining apparatus including divertor means for diverting plasma confined within the interior of said vacuum vessel to a strike zone on at least one divertor target, said plasma pump comprising: an entrance aperture facing said at least one divertor target through which a plasma is to be pumped said divertor target comprising an electrode positioned proximate to said entrance aperture, said electrode being electrically insulated from the electrically conductive walls of said vacuum vessel; and  means for applying an electric field E between said electrode and said electrically conductive walls of said vacuum vessel;  said electric field combining with said magnetic fields so as to impart an E.times.B drift velocity to said plasma that drives said plasma through said entrance aperture.  electrode means for establishing an electric field E which interacts with a magnetic field B to electromagnetically drive a plasma towards an aperture point, said electrode means further comprising a divertor target; and  duct means for collecting said plasma at said aperture point.  a ring electrode encircling a major axis of a tokamak, said ring electrode being electrically insulated from a conductive wall of said tokamak, said ring electrode being positioned to interface with a separatrix of a poloidal divertor used within said tokamak, said separatrix having a strike position incident with said ring electrode, said aperture point being adjacent said ring electrode and said strike position, and  biasing means for applying an electric potential to said ring electrode relative to said conductive wall of said tokamak structure.  (a) positioning a ring electrode near a strike position such that said ring electrode makes contact with plasma in a SOL and such that the separatrix of a poloidal divertor is incident upon said ring electrode:  (b) insulating a plasma-facing side of said ring electrode from the vessel walls and duct means of the tokamak system with a first insulator;  (c) insulating a portion of a wall of the vessel adjacent said strike position but spaced apart from said ring electrode with a second insulator;  (d) positioning an entrance aperture of said duct means intermediate to said ring electrode and said second insulator; and  (e) applying an electric field E between said ring electrode and said vessel wall, whereby an E.times.B drift is developed which drives plasma being diverted towards said strike position through said entrance aperture. 2. The plasma pump as set forth in claim 1 wherein said vacuum vessel comprises a toroid, and wherein said plasma-confining apparatus confines said plasma to a toroidal shape within said vacuum vessel, said electrode comprising a ring electrode. 3. The plasma pump as set forth in claim 2 further including first electrical insulating means (63) positioned between one plasma-facing edge of said ring electrode and said electrically conductive walls of said toroidal vacuum vessel. 4. The plasma pump as set forth in claim 3 further including second electrical insulating means (64) positioned on an inner surface of said electrically conductive walls of said toroidal vacuum vessel facing said ring electrode. 5. The plasma pump as set forth in claim 1 wherein said means for applying the electric field E between said electrode and the electrically conductive walls of said vacuum vessel includes means for applying an electrical potential to said electrode wherein said electrical potential applied to said electrode has a desired polarity relative to the electrical potential of said electrically conductive walls for said vacuum vessel. 6. The plasma pump as set forth in claim 1 wherein said divertor means includes means for sweeping a plasma strike zone across said electrode, the geometry of said strike zone relative to said entrance aperture thereby changing; and means for selectively adjusting the magnitude of said applied electric field E so as to render said plasma pump substantially geometry-insensitive. 7. A plasma pump for use in a plasma-confining device, said plasma-confining device including means for generating a magnetic field B to confine a plasma to a prescribed volume within said plasma-confining device, said plasma pump comprising: 8. The plasma pump as set forth in claim 7 wherein said plasma-confining device comprises a tokamak, and wherein said electrode means comprises: 9. The plasma pump as set forth in claim 8 further including first insulating means for electrically insulating plasma-facing sides of said ring electrode. 10. The plasma pump as set forth in claim 9 further including second insulating means spaced apart from said ring electrode for electrically insulating a portion of said tokamak structure facing said ring electrode, said aperture point being located intermediate said ring electrode and said second insulating means. 11. The plasma pump as set forth in claim 8 wherein the polarity of said electric potential applied to said ring electrode by said biasing means relative to the electric potential of said conductive wall of said tokamak structure is selected in conjunction with the polarity of said toroidal magnetic field such that the E.times.B/B.sup.2 plasma flow velocity is directed toward said aperture point. 12. The plasma pump as set forth in claim 8 wherein said ring electrode includes coolant channels formed therein such that a coolant may be circulated through said channels in order to remove heat from said ring electrode. 13. A method for removing plasma exhaust from a tokamak system, said tokamak system including a vessel and means for generating a magnetic field B that confines plasma within a toroidal volume within said vessel; said tokamak system further including a poloidal divertor having a separatrix X-point and scrape-off layer (SOL) associated therewith, with plasma being diverted by said poloidal divertor along said SOLs to a strike position adjacent said X-point; said tokamak system further having duct means for collecting plasma exhaust; said method comprising the steps of: 14. The method as set forth in claim 13 wherein step (e) includes applying a biasing potential to said ring electrode having a polarity selected in conjunction with the sign of a toroidal magnetic field such that the E.times.B/B.sup.2 plasma flow velocity is directed toward said entrance aperture.