摘要:
A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and/or recycled for subsequent use within the same blanket region. Thermonuclear ignition of the plasma is obtained by feeding neutral fusible gas into the plasma in a controlled manner such that charged particle heating produced by the fusion reaction is utilized to bootstrap the device to a region of high temperatures and high densities wherein charged particle heating is sufficient to overcome radiation and thermal conductivity losses. The high density plasma produces a large radiation and particle flux on the first wall of the plasma core region thereby necessitating replacement of the core from the blanket region from time to time. A series of potentially disposable and replaceable central core regions are disclosed for a large-scale economical electrical power generating plant.
摘要:
The inductively formed spheromak plasma can be maintained in a highly stable and controlled fashion. Steady-state operation is obtained by forming the plasma in the linked mode, then oscillating the poloidal and toroidal fields such that they have different phases. Preferably, the poloidal and magnetic fields are 90.degree. out of phase.
摘要:
A fusion reactor device in which the toroidal magnetic field and at least a portion of the poloidal magnetic field are provided by a single set of modular coils. The coils are arranged on the surface of a low aspect ratio toroid in planes having the cylindrical coordinate relationship .phi.=.phi..sub.i +kz where k is a constant equal to each coil's pitch and .phi..sub.i is the toroidal angle at which the i'th coil intersects the z=o plane. The device may be described as a modular, high beta torsation whose screw symmetry is pointed along the systems major (z) axis. The toroid defined by the modular coils preferably has a racetrack minor cross section. When vertical field coils and preferably a toroidal plasma current are provided for magnetic field surface closure within the toroid, a vacuum magnetic field of racetrack shaped minor cross section with improved stability and beta valves is obtained.
摘要:
A fusion power generating device is disclosed having a relatively small and inexpensive core region which may be contained within an energy absorbing blanket region. The fusion power core region contains apparatus of the toroidal type for confining a high density plasma. The fusion power core is removable from the blanket region and may be disposed and/or recycled for subsequent use within the same blanket region. Thermonuclear ignition of the plasma is obtained by feeding neutral fusible gas into the plasma in a controlled manner such that charged particle heating produced by the fusion reaction is utilized to bootstrap the device to a region of high temperatures and high densities wherein charged particle heating is sufficient to overcome radiation and thermal conductivity losses. The high density plasma produces a large radiation and particle flux on the first wall of the plasma core region thereby necessitating replacement of the core from the blanket region from time to time. A series of potentially disposable and replaceable central core regions are disclosed for a large-scale economical electrical power generating plant.
摘要:
Toroidal field coils are interlaced with other toroidal structures and are operated under supercooled conditions. To facilitate demounting the toroidal field coils, which are supercooled, they are made in the form of connected segments constituting coils of polygonal form. The segments may be rectilinear in form, but some may also be U-shaped or L-shaped. The segments are detachable from one another and are supported in load relieving manner. Power devices are used to displace the segments to facilitate removal of the coils from the aforesaid toroidal structures and to provide for the accommodation of dimensional changes and stresses due to thermal and magnetic conditions. The segments are formed of spaced parallel conductive slabs with the slabs of one segment being interdigitated with the slabs of the adjacent segment. The interdigitated slabs may be soldered together or slidingly engaged. The slabs are shaped to accommodate superconductors and to provide passages for a cooling medium. The slabs are moreover separated by insulator slabs with which they form a coil structure which is jacketed.
摘要:
Method and apparatus for initially producing a sharp boundaried theta-pinch plasma, and subsequently relaxing the current sheath of the plasma to provide a diffuse-pinch plasma, in which the diffuse pinch plasma has a doublet or higher multiplet magnetic confinement configuration with one or more internal separatrices, and in which the initially formed, sharp-boundaried plasma is provided with a current sheath having a contour corresponding to a flux surface of the doublet or multiplet configuration.
摘要:
A FUSION REACTOR IN WHICH THE THERMONUCLEAR PLASMA IS PRODUCED BY A STAGED THETA PINCH HAVING TWO DISTINCT ENERGY SOURCES, ONE FOR SHOCK HEATING AND ONE FOR ADIABATIC COMPRESSION. IN THE REACTOR CORE THE PLASMA IS SURROUNDED BY A THIN LIQUID-METAL-COOLED VACUUM WALL WHICH ALSO SERVES AS A SHOCK HEATING COIL. THIS COIL IS DRIVEN BY HIGH VOLTAGE CIRCUITS WHOSE ENERGY CONTENT IS ONLY A FEW PERCENT OF THAT OF THE TOTAL SYSTEM. THE LOW-VOLTAGE COMPRESSIONAL AND CONFINING MAGNETIC FIELD, WHOSE ENERGY IS PREPONDERANT, HAS A RISETIME OF A FEW MILLISECONDS AND IS GENERATED BY A MULTITURN CIOL WHOSE RADIUS IS SUBSTANTIALLY GREATER THEN THAT OF THE SHOCK-HEATING COIL. THE COMPRESSION COIL OPERATES NEAR ROOM TEMPERATURE, AND THE SYSTEM IS SUFFICIENTLY ECONOMICAL OF JOULE LOSSES THAT THEY CAN LARGELY BE MADE UP BY DIRECT ENERGY CONVERSION FROM THE EXPANSION OF THE HIGH-BETA PLASMA AGAINST THE MAGNETIC FIELD DURING THE BURING PULSE. THE COMPRESSION COIL IS PROTECTED FROM EXCESSIVE NUCLEAR RADIATION AND HEATING BY A PORTION O THE NEUTRON-MODERATING, TRITIUM-BREEDING BLANKET. THIS INNER PORTON O THE BLANKET OPERATES AT A TEMPERATURE AS HIGH AS ABOUT 800*C. MAGNETIC ENERGY IS SWITCHED REVERSIBLY INTO THE COMPRESSION COIL FROM A CRYOGENIC MAGNETIC ENERGY STORE SITUATED OUTSIDE THE REACTOR CORE. THE COMPRESSION MAGNETIC ENERGY IS RETURNED TO THE STORE AT THE END OF EACH POWER PULSE, WHICH LASTS APPROXIMATELY 100 MSEC. THESE PULSES ARE SEPARATED BY TIMES OF THE ORDER OF A FEW SEC. REFUELING ANY FLUSHING OF THE SPENT PLASMA BETWEEN BURNING PULSES ARE ACCOMPLISHED BY FLOWING D-T GAS THROUGH THE VACUUM CHAMBER.
摘要:
PLASMA IS PRINCIPALLY CONFINED IN A TOROIDAL CONFIGURATION BY A STATIC MAGNETIC FIELD. FOR STABILISING THE PLASMA, A RADIOFREQUENCY ELECTROMAGNETIC FIELD MOVING FASTER THAN THE IONS IN THE PLASMA AND OF FREQUENCY IN THE REGION OF 1 MEGAHERTZ IS APPLIED. FOWER FOR GENERATING THE RADIOFREQUENCY FIELD IS COUPLED INTO AN ENDLESS PATH FOR CONDUCTING ELECTROMAGNETIC POWER, THE PATH HAVING A DISTRIBUTED INDUCTANCE AND CAPACITANCE SUCH THAT IT IS A CIRCULT WHICH RESONATES AT THE FREQUENCY OF THE ELECTROMAGNETIC FIELD.