Helical field stabilization of plasma devices
AssigneeGeneral Atomic Company
InventorTihiro Ohkawa
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AssigneeGeneral Atomic Company
InventorTihiro Ohkawa
Estimating the term…
A toroidal plasma device has a toroidal confinement vessel defining a toroidal space and confining ionized gas therein. A solenoid which links the toroidal space induces a toroidal electric field therein to produce plasma current. A plurality of first windings are wound substantially helically around the vessel substantially equally spaced around its minor circumference. A plurality of second windings are wound substantially helically around the vessel substantially midway between successive first windings. Direct current is passed through the respective first and second windings in opposite directions with the current in the respective first and second windings equal or slightly unbalanced. The currents in the first and second windings produce a helical magnetic field. The combination of the poloidal magnetic field from the plasma current with this helical magnetic field produces a separatrix in the toroidal space, this separatrix defining a closed surface which limits and encloses a region within which closed and nested magnetic flux surfaces exist. The sense of rotation of the first and second windings and the direction of the plasma current produces a variation in the safety fractor q with minor radius at any poloidal angle, whereby the sign of q reverses near the outer edge of the plasma, q being an average over a flux surface of the number of transit made around the torus in the toroidal direction by a magnetic flux line in making a single transit in the poloidal direction. The sign of q is determined by the sense of the direction in which the toroidal transit is made.
A toroidal plasma device comprising
A toroidal plasma device comprising
A toroidal plasma device comprising
A plasma device comprising
A plasma device comprising
A method of operating a toroidal plasma device having a toroidal confinement vessel with walls defining a toroidal space and confining gas therein, said method comprising
A method of operating a toroidal plasma device having a toroidal confinement vessel with walls defining a toroidal space and confining gas therein, said method comprising
A method of operating a toroidal plasma device having a toroidal confinement vessel with walls defining a toroidal space and confining gas therein, said method comprising
A method of operating a plasma device having a confinement vessel with an axis and an axial direction with walls surrounding the axis thereof for defining a space and confining gas therein, said method comprising
A method of operating a plasma device having a confinement vessel for defining a space having an axis and an axial direction and confining gas therein, said method comprising
Dependencies are inferred from the claim text.
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No related US applications are recorded in the indexed filing history.
Using externally-applied magnetic fields only , e.g. Q-machines, Yin-Yang, base-ball: wherein the containment vessel forms a closed or nearly…
Energy generation of nuclear origin: nuclear fusion reactors
Plasma technique
Clean energy generation and storage
Term ended 29 Jan 1999 (estimated)
USPTO file history isn’t available for this patent, so only indexed dates are shown.
This invention relates generally to plasma devices and particularly to the stabilization of toroidal fusion devices. More particularly, the present invention relates to the combination of helical magnetic field and a poloidal magnetic field for the stabilization of such devices.
Toroidal plasma devices are devices in which plasma is created in a toroidal space and is confined therein by appropriate confining fields. Such devices are useful in the study and analysis of plasmas and particularly in the generation, confinement, study and analysis of hydrogenous plasmas. Such devices are useful in respect to plasma devices for the reaction of deuterium and tritium, with the production of high energy neutrons as reaction products. The present invention finds particular utility in such devices and their applications, including experimental devices and the use thereof in experimentation and investigation in respect to toroidal plasma devices.
The problems in fusion devices are largely in heating the plasma to a high enough temperature to enable the desired reactions to occur and to confine the heated plasma for a time long enough to release energy in excess of that required to produce the reactions. The present invention is directed to the confinement of such plasma.
Thus, it is a primary object of the present invention to provide for confinement of plasma in a toroidal plasma device by the combination of a poloidal magnetic field produced by plasma current and a helical magnetic field produced by helical windings. Other objects and advantages of the present invention will become evident from the consideration of the following detailed description, particularly when taken in connection with the accompanying drawings in which:
FIG. 1 is an isometric view of one form of toroidal fusion device utilizing a plasma confinement system according to the present invention, with certain parts shown diagrammatically and with the support structure, auxiliary turns and vacuum headers broken away;
FIG. 2 is a sectional view of one half of the device shown in FIG. 1, taken along the major axis of the torus, with certain parts of the support structure and vacuum system shown in elevation;
As illustrated in FIGS. 1 and 2, a toroidal plasma device 10 includes a primary confinement vessel in the form of a toroidal liner 12 which confines and defines a primary toroidal chamber 14 containing appropriate gas at a suitable low pressure. In the design illustrated, the liner 12 is made of thin wall stainless steel which permits rapid penetration of toroidal electric field to start up and drive plasma current in the primary toroidal chamber 14. The toroidal liner 12 is disposed within and supported from a secondary confinement vessel in the form of a toroidal shell 16. The shell 16 as shown is formed of a relatively thick copper wall forming a secondary toroidal chamber 18. The secondary chamber 18 is evacuated through conduits 20 and a header 22 by a vacuum pump means not shown. The primary chamber 14 is evacuated through conduits 24 and a header 26 by vacuum pump means also not shown.
As shown in FIGS. 4 and 5, the shell 16 includes a ceramic break 28 which serves to interrupt the toroidal conductive path around the shell 16 which would otherwise short circuit the toroidal conductive path through the plasma. The conductance of the liner 12 is sufficiently low in respect to the conductance of the plasma as not to be wasteful of energy. That is, a magnetic field may readily penetrate the conductive shell 16 because of the ceramic break 28 and penetrate the liner 12 because it is relatively thin and of lower conductivity than the material forming the shell 16. At the same time, the liner 12 provides an electrical bridge across the ceramic break 28 and isolates the ionized plasma from the electrical break thereby formed in the conductive shell 16. At the same time, the conducting shell 16 aids in stabilization of the plasma by repelling plasma current trying to move toward the wall of the shell 16.
As with tokamak devices, the plasma current is produced by a toroidal electric field induced by a solenoid coil 30 disposed axially of the major axis of the toroidal liner 12 and inside the torus. The toroidal electric field is created by operation of the solenoid coil 30 and additional turns 32 disposed to channel the poloidal flux outside the liner 12. The solenoid coil 30 and additional turns 32 are energized in a conventional manner by a power supply not shown, whereby the change in electrical current in the coil causes a change in magnetic flux linking the single turn secondary formed by the liner 12 and its contents. The change in flux, in turn, generates plasma current within the primary chamber 14.