Patent classifications
G21B1/11
PASSIVE MAGNETIC SHIELDING OF STRUCTURES IMMERSED IN PLASMA USING SUPERCONDUCTORS
A fusion reactor includes a fusion plasma reactor chamber. A magnetic coil structure is disposed inside of the fusion plasma reactor chamber, and a structural component is also disposed inside of the fusion plasma reactor chamber. The structural component couples the magnetic coil structure to the fusion plasma reactor chamber. A superconducting material is disposed at least partially within the structural component. A plurality of cooling channels are disposed at least partially within the structural component. An insulating material is disposed at least partially within the structural component.
PASSIVE MAGNETIC SHIELDING OF STRUCTURES IMMERSED IN PLASMA USING SUPERCONDUCTORS
A fusion reactor includes a fusion plasma reactor chamber. A magnetic coil structure is disposed inside of the fusion plasma reactor chamber, and a structural component is also disposed inside of the fusion plasma reactor chamber. The structural component couples the magnetic coil structure to the fusion plasma reactor chamber. A superconducting material is disposed at least partially within the structural component. A plurality of cooling channels are disposed at least partially within the structural component. An insulating material is disposed at least partially within the structural component.
Plasma confinement device with helical current and fluid flow
A device and method for generating plasma conditions for deuterium-tritium and advanced fuel thermonuclear fusion consisting of an inner helicity-containing plasma such as a spheromak compact toroid bounded by a plurality of outer cusped magnetic fields. Helicity driven by steady-inductive helicity injectors energizes the plasmoid with helicity. The device further includes means for driving fluid rotation about the device axis, about the device magnetic axis, and means for a hot electron sheath. Means are also provided for reducing particle losses out through the open cusp field lines through helicity injector rectification.
Plasma confinement device with helical current and fluid flow
A device and method for generating plasma conditions for deuterium-tritium and advanced fuel thermonuclear fusion consisting of an inner helicity-containing plasma such as a spheromak compact toroid bounded by a plurality of outer cusped magnetic fields. Helicity driven by steady-inductive helicity injectors energizes the plasmoid with helicity. The device further includes means for driving fluid rotation about the device axis, about the device magnetic axis, and means for a hot electron sheath. Means are also provided for reducing particle losses out through the open cusp field lines through helicity injector rectification.
Plasma creation and heating via magnetic reconnection in an encapsulated linear ring cusp
In one embodiment, a fusion reactor includes an enclosure, one or more internal magnetic coils suspended within an interior of the enclosure and co-axial with a center axis of the enclosure, one or more encapsulating magnetic coils co-axial with the center axis of the enclosure, the encapsulating magnetic coils having a larger diameter than the internal magnetic coils, one or more mirror magnetic coils co-axial with the center axis of the enclosure, and one or more magnetic reconnection coils co-axial with the center axis of the enclosure, wherein the one or more magnetic reconnection coils, when pulsed by a power source, are disposed to reconfigure one or more magnetic fields within the enclosure. The reconfiguration, or magnetic reconnection, of the one or more magnetic fields is disposed to increase energy in the magnetic fields, thereby facilitating the conditions operable to generate plasma, and further, when the magnetic fields are collapsed, releasing the energy into the plasma.
Plasma creation and heating via magnetic reconnection in an encapsulated linear ring cusp
In one embodiment, a fusion reactor includes an enclosure, one or more internal magnetic coils suspended within an interior of the enclosure and co-axial with a center axis of the enclosure, one or more encapsulating magnetic coils co-axial with the center axis of the enclosure, the encapsulating magnetic coils having a larger diameter than the internal magnetic coils, one or more mirror magnetic coils co-axial with the center axis of the enclosure, and one or more magnetic reconnection coils co-axial with the center axis of the enclosure, wherein the one or more magnetic reconnection coils, when pulsed by a power source, are disposed to reconfigure one or more magnetic fields within the enclosure. The reconfiguration, or magnetic reconnection, of the one or more magnetic fields is disposed to increase energy in the magnetic fields, thereby facilitating the conditions operable to generate plasma, and further, when the magnetic fields are collapsed, releasing the energy into the plasma.
Plasma Creation and Heating Via Magnetic Reconnection in an Encapsulated Linear Ring Cusp
In one embodiment, a fusion reactor includes an enclosure, one or more internal magnetic coils suspended within an interior of the enclosure and co-axial with a center axis of the enclosure, one or more encapsulating magnetic coils co-axial with the center axis of the enclosure, the encapsulating magnetic coils having a larger diameter than the internal magnetic coils, one or more mirror magnetic coils co-axial with the center axis of the enclosure, and one or more magnetic reconnection coils co-axial with the center axis of the enclosure, wherein the one or more magnetic reconnection coils, when pulsed by a power source, are disposed to reconfigure one or more magnetic fields within the enclosure. The reconfiguration, or magnetic reconnection, of the one or more magnetic fields is disposed to increase energy in the magnetic fields, thereby facilitating the conditions operable to generate plasma, and further, when the magnetic fields are collapsed, releasing the energy into the plasma.
Plasma Creation and Heating Via Magnetic Reconnection in an Encapsulated Linear Ring Cusp
In one embodiment, a fusion reactor includes an enclosure, one or more internal magnetic coils suspended within an interior of the enclosure and co-axial with a center axis of the enclosure, one or more encapsulating magnetic coils co-axial with the center axis of the enclosure, the encapsulating magnetic coils having a larger diameter than the internal magnetic coils, one or more mirror magnetic coils co-axial with the center axis of the enclosure, and one or more magnetic reconnection coils co-axial with the center axis of the enclosure, wherein the one or more magnetic reconnection coils, when pulsed by a power source, are disposed to reconfigure one or more magnetic fields within the enclosure. The reconfiguration, or magnetic reconnection, of the one or more magnetic fields is disposed to increase energy in the magnetic fields, thereby facilitating the conditions operable to generate plasma, and further, when the magnetic fields are collapsed, releasing the energy into the plasma.
Apparatus And Method For Sourcing Fusion Reaction Products
An apparatus and method for sourcing nuclear fusion products uses an electrochemical loading process to load low-kinetic-energy (low-k) light element particles into a target electrode, which comprises a light-element-absorbing material (e.g., Palladium). An electrolyte solution containing the low-k light element particles is maintained in contact with a backside surface of the target electrode while a bias voltage is applied between the target electrode and an electrochemical anode, thereby causing low-k light element particles to diffuse from the backside surface to an opposing frontside surface of the target electrode. High-kinetic-energy (high-k) light element particles are directed against the frontside, thereby causing fusion reactions each time a high-k light element particle operably collides with a low-k light element particle disposed on the frontside surface. Fusion reaction rates are controlled by adjusting the bias voltage.
BIFILAR WINDING SYSTEM FOR MANUFACTURE OF POLOIDAL FIELD SUPERCONDUCTING MAGNETS FOR NUCLEAR FUSION
Disclosed is a bifilar winding system for the manufacture of poloidal field superconducting magnets for nuclear fusion, including two superconducting coil winding production lines which are symmetrically arranged, a dropping fixture, a rotary platform and a winding mold, and an automatic control system. Each of the two winding production lines includes a conductor unwinding device, a straightener, an ultrasonic cleaning machine, a sandblasting and cleaning machine, a bending machine, an inter-turn insulation taping machine. During the winding of a coil, a superconducting conductor is unwound by the conductor unwinding device under the control of the automatic control system, then straightened, ultrasonically cleaned, sandblasted and cleaned, and bent into a desired radius, then wrapped with multiple layers of insulating tape by the inter-turn insulation taping machine, and finally fixed, by the dropping fixture, precisely on the rotary platform at a correct position within a profile of the winding mold.