Patent classifications
H05H3/06
Inertial Electrostatic Confinement Fusion Device
An inertial electrostatic confinement fusion device has a body defining an internal vacuum chamber cavity, the chamber cavity having attached a means to evacuate atmosphere to vacuum conditions, the chamber cavity further having attached a means to inject a nuclear fusion fuel source at a metered rate, the chamber cavity further having within it a plurality of electrodes connected to a high voltage alternating current power supply such that at least one pair of said electrodes consistently have electrical charge of opposite polarity and equal magnitude, having a minimum distance between oppositely charged electrodes defining an electrode gap, the power supply further alternating the electrical current at a rate faster than ions of the nuclear fusion fuel source can traverse the electrode gap when accelerated by the applied voltage.
Inertial Electrostatic Confinement Fusion Device
An inertial electrostatic confinement fusion device has a body defining an internal vacuum chamber cavity, the chamber cavity having attached a means to evacuate atmosphere to vacuum conditions, the chamber cavity further having attached a means to inject a nuclear fusion fuel source at a metered rate, the chamber cavity further having within it a plurality of electrodes connected to a high voltage alternating current power supply such that at least one pair of said electrodes consistently have electrical charge of opposite polarity and equal magnitude, having a minimum distance between oppositely charged electrodes defining an electrode gap, the power supply further alternating the electrical current at a rate faster than ions of the nuclear fusion fuel source can traverse the electrode gap when accelerated by the applied voltage.
MODERATOR FOR MODERATING NEUTRONS
Disclosed is a moderator for moderating neutrons, including a substrate and a surface treatment layer or a dry inert gas layer or a vacuum layer coated on the surface of the substrate, wherein the substrate is prepared from a moderating material by a powder sintering device through a powder sintering process from powders or by compacting powders into a block, and the moderating material includes 40% to 100% by weight of aluminum fluoride; wherein the surface treatment layer is a hydrophobic material; and the surface treatment layer or the dry inert gas layer or the vacuum layer is used for isolating the substrate from the water in the environment in which the substrate is placed. The surface treated moderator can avoid the hygroscopic or deliquescence of the moderating material during use, improve the quality of the neutron source and prolong the service life.
MODERATOR FOR MODERATING NEUTRONS
Disclosed is a moderator for moderating neutrons, including a substrate and a surface treatment layer or a dry inert gas layer or a vacuum layer coated on the surface of the substrate, wherein the substrate is prepared from a moderating material by a powder sintering device through a powder sintering process from powders or by compacting powders into a block, and the moderating material includes 40% to 100% by weight of aluminum fluoride; wherein the surface treatment layer is a hydrophobic material; and the surface treatment layer or the dry inert gas layer or the vacuum layer is used for isolating the substrate from the water in the environment in which the substrate is placed. The surface treated moderator can avoid the hygroscopic or deliquescence of the moderating material during use, improve the quality of the neutron source and prolong the service life.
Neutron Source and Method of Producing a Neutron Beam
The invention relates to a neutron source, containing a first proton accelerator for producing a first proton beam having a first energy and a first target for producing a first neutron beam, which first target is connected to the first proton accelerator by a first beam trajectory, and at least one first neutron beam channel serving for guiding the protons exiting the first target, characterised by a second proton accelerator for producing a higher, second energy proton beam from the first proton beam, which second proton accelerator is linked to the first proton accelerator by a second proton accelerator, furthermore the first beam trajectory and the second beam trajectory contain a proton beam deflector arranged on a common section, set up to convey the proton beam along the first beam trajectory to the first target in a first operation state, and along the second beam trajectory to the second proton accelerator in a second operation state, and contain a second target for producing a second neutron beam, which second target is linked to the second proton accelerator by a third beam trajectory. In a similar way the neutron source is also conceivable with a third or even more accelerators and targets.
Neutron Source and Method of Producing a Neutron Beam
The invention relates to a neutron source, containing a first proton accelerator for producing a first proton beam having a first energy and a first target for producing a first neutron beam, which first target is connected to the first proton accelerator by a first beam trajectory, and at least one first neutron beam channel serving for guiding the protons exiting the first target, characterised by a second proton accelerator for producing a higher, second energy proton beam from the first proton beam, which second proton accelerator is linked to the first proton accelerator by a second proton accelerator, furthermore the first beam trajectory and the second beam trajectory contain a proton beam deflector arranged on a common section, set up to convey the proton beam along the first beam trajectory to the first target in a first operation state, and along the second beam trajectory to the second proton accelerator in a second operation state, and contain a second target for producing a second neutron beam, which second target is linked to the second proton accelerator by a third beam trajectory. In a similar way the neutron source is also conceivable with a third or even more accelerators and targets.
SYSTEMS AND METHODS EMPLOYING INTERCHANGEABLE ION BEAM TARGETS
Provided herein are systems and methods for generating a plurality of different monoenergetic neutron energies using a plurality of interchangeable ion beam targets. In certain embodiments, each of the plurality of ion beam targets is configured to generate a monoenergetic energy value that is at least 100 kiloelectron volts (keV) different from the other ion beam targets. In some embodiments, the ion beam targets are composed of LiF, TiD.sub.1.5-1.8, TiT.sub.1-2, ErD.sub.1.5, ErT, or Li.
SYSTEMS AND METHODS EMPLOYING INTERCHANGEABLE ION BEAM TARGETS
Provided herein are systems and methods for generating a plurality of different monoenergetic neutron energies using a plurality of interchangeable ion beam targets. In certain embodiments, each of the plurality of ion beam targets is configured to generate a monoenergetic energy value that is at least 100 kiloelectron volts (keV) different from the other ion beam targets. In some embodiments, the ion beam targets are composed of LiF, TiD.sub.1.5-1.8, TiT.sub.1-2, ErD.sub.1.5, ErT, or Li.
NEUTRON GENERATING TARGET FOR NEUTRON BEAM SYSTEMS
Embodiments that are directed to a target for producing a high epithermal neutron yield for boron-neutron capture therapy (BNCT) treatments are disclosed. The target includes a thin flat film of solid lithium mounted onto a heat-removal support structure that is cooled with a liquid coolant and configured to maintain the turbulent flow regime for a liquid coolant and distribute the flow of coolant directed at the center of the support structure toward a periphery of the support structure via a plurality of channels formed in the support structure. The support structure includes a nozzle located at its center to direct coolant flow outwardly from the center to avoid stagnant water flow at the center of the support structure. Systems, device, and methods utilizing the approaches are also described.
NEUTRON GENERATING TARGET FOR NEUTRON BEAM SYSTEMS
Embodiments that are directed to a target for producing a high epithermal neutron yield for boron-neutron capture therapy (BNCT) treatments are disclosed. The target includes a thin flat film of solid lithium mounted onto a heat-removal support structure that is cooled with a liquid coolant and configured to maintain the turbulent flow regime for a liquid coolant and distribute the flow of coolant directed at the center of the support structure toward a periphery of the support structure via a plurality of channels formed in the support structure. The support structure includes a nozzle located at its center to direct coolant flow outwardly from the center to avoid stagnant water flow at the center of the support structure. Systems, device, and methods utilizing the approaches are also described.