61results about "Neutron sources" patented technology

This invention relates to the field of neutron source technology, and particularly to a controllable isotope neutron source device based on ion migration and a method for generating neutrons. The device includes a casing, inside which are a target material module, a target ion migration system, a safety module, and an alpha particle source term. The target material module provides target nuclide ions. The alpha particle source term includes alpha radioactive nuclide material and target nuclide intercalation material. The safety module is composed of target nuclide intercalation material. The target ion migration system is connected to an external control field. Target nuclide ions migrate through the target ion migration system within the safety module and the alpha particle source term. This invention enables active controllability of the isotope neutron source, significantly improving safety. By ensuring sufficient contact between alpha particles and target nuclides to form a molecular intercalation structure, the (α,n) reaction efficiency is greatly improved. Furthermore, this neutron source can be used in combination with multiple modules according to application requirements, effectively increasing the neutron output flux.

The invention belongs to the technical field of nuclear, and relates to a high-precision full-size conical neutron conduit regulation and control system and an integration method thereof. The system is supported by a bottom storage cabinet, a marble base, a top integration bottom positioning part, two groups of horizontal and top feeding regulation and control components and a positioning block are arranged on the bottom storage cabinet, a conical standard sample block is arranged between the components, and a pneumatic system is arranged in the bottom storage cabinet; the whole process of the system is integrally spliced, an external auxiliary structure is not needed, and the operation efficiency is improved; multi-specification adaptation and size expansibility are achieved, and catheters with different opening sizes can be rapidly switched to be spliced; the positioning adsorption unit performs processing according to a set taper to meet diversified requirements; a micrometer assembly and the like ensure that the splicing form and location tolerance is less than or equal to 20 microns, and the assembly error is reduced; the temperature deformation influence is reduced through material and process innovation, and the splicing quality is guaranteed; standardized interfaces are convenient to disassemble, assemble and maintain, and the technical threshold is reduced by manual regulation.

The invention discloses a neutron source assembly which comprises a neutron source rod body, a lower end plug, a composite upper end plug and a guide cylinder, and the neutron source rod body comprises a neutron source rod end plug, a neutron source rod cladding tube, an upper reflecting layer, a lower reflecting layer, a source box and a matched end plug. The neutron source assembly adopts the rod-in-rod design, the possibility of abrasion of the neutron source rod body in the transportation process and the like can be reduced, the neutron source leakage risk is reduced, the counterweight design of the composite upper end plug can counteract the buoyancy of a coolant in a reactor, and it is ensured that the neutron source assembly smoothly falls to the bottom and keeps stable; the neutron source rod body can be used in a pressurized water reactor and can also be used in a liquid heavy metal reactor. Meanwhile, the sealing packaging structure of the neutron source rod body can reduce the risk of neutron source leakage caused by abrasion in the transportation and in-reactor operation process, the arrangement of the guide cylinder provides guidance for the assembly of the neutron source rod body, and the probability of collision damage of the neutron source rod body in the assembly process is reduced.

A plasma focus system for neutron production is disclosed that includes an electrode assembly having an inner electrode extending along a pinch axis from a discharge end to a focus end, and an outer electrode surrounding the inner electrode to define a plasma channel for receiving a gas containing neutronic fusion fuel. The system also includes a power supply unit for applying a discharge driving signal to the electrodes, which causes the gas to be ionized into a plasma current sheath at the discharge end that flows along the plasma channel to reach the focus end where the sheath collapses toward the pinch axis to form a plasma pinch that generates fusion neutrons. The inner electrode has a tapered tip at the focus end that is configured to increase a speed of the sheath sufficiently to reach a pinch temperature at which the fusion neutrons are predominantly of thermonuclear origin.

Maintainability is to be improved. A radio frequency quadrupole linear accelerator includes a tubular housing part having an outer peripheral surface at which two pairs of openings extending in an axial direction are formed facing each other, and a plurality of first vane electrodes inserted into the respective openings of the tubular housing part from outside toward an axial center, detachably attached to the openings, and disposed facing each other.

Provided herein are neutron imaging systems (e.g., radiography and tomography) systems and methods that provide, for example, high-quality, high throughput 2D and 3D fast or thermal neutron and / or X-ray images. Such systems and methods find use for the commercial-scale imaging of industrial components. In certain embodiments, provided herein are system comprising a plurality of independent neutron absorber-lined collimators (e.g., 4 or more collimators) extending outwards from a central neutron source assembly.

Provided herein are neutron imaging systems (e.g., radiography and tomography) systems and methods that provide, for example, high-quality, high throughput 2D and 3D fast or thermal neutron and / or X-ray images. Such systems and methods find use for the commercial-scale imaging of industrial components. In certain embodiments, provided herein are system comprising a plurality of independent neutron absorber-lined collimators (e.g., 4 or more collimators) extending outwards from a central neutron source assembly.

In particular, methods and systems for the periodic enrichment of rare earth elements and isotopes are provided. A crucible, or a tube or ampoule which may have two coaxially opposing crucibles in fluid communication, is used to hold a source material in a vacuum and irradiate the source material to enrich it with respect to a product material. Source material (e.g., 176 Irradiating with Yb-enriched Yb to produce a product (for example, 177 After obtaining Lu), the mixture may be sublimated to remove most of the source material and concentrate the product material by, for example, heating the lower part of the tube and cooling the upper part of the tube to condense the sublimated source material at the top of the tube. Subsequently, the concentrated product material may be purified, or the solidified source structure may be reused in an irradiation / sublimation cycle to further enrich and concentrate the product material.

The invention discloses a laser neutron yield increasing method based on a composite conversion target, which comprises the following steps of: arranging a plurality of elements to form the composite conversion target, bombarding the composite conversion target by using a deuterium ion beam obtained by interaction of laser and a heavy water liquid film target, and realizing neutron yield increasing through nuclear reaction section optimization; elements in the composite conversion target comprise at least two of T, D, < 7 > Li and < 9 > Be. According to the laser neutron yield increasing method based on the composite conversion target, the neutron yield and the average flux of a repetition frequency laser neutron source method are greatly increased, and the problem of instability in the continuous production process of a heavy water liquid film target is solved.

The invention discloses a solid neutron source device with potential diversion and magnetic field screening functions and a control method. The device comprises an ion generation structure, a potential diversion structure, a magnetic field screening structure, a neutron target and an insulating shell, the ion generation structure generates mixed ions under the action of the outside, the mixed ions form regular beams under the action of the potential diversion structure and enter the magnetic field screening structure, and due to the fact that different ions show different motion characteristics in a magnetic field, screening is carried out through an insulation pole plate with long rectangular holes. And finally, ion receiving and neutron excitation are completed under the action of strong potential carried by the neutron target. According to the invention, the loss caused by ion generation is effectively controlled through a potential diversion structure, and the utilization efficiency of ions and the neutron yield are improved by adopting a control method that the potential is continuously adjustable. Meanwhile, through a magnetic field screening structure, effective separation and screening of mixed ions are achieved, a control method with a continuously adjustable magnetic field is adopted, the screening range is wide, and the service life of a neutron source is prolonged.

To provide an irradiation method and system for irradiating a target volume.SOLUTION: An irradiation method comprises: providing thermal neutron absorbing nuclides (such as in a form of a high neutron cross-section agent) at a target volume; and producing neutrons by irradiating nuclei in or adjacent to the target volume with a beam of particles consisting of any one or more of protons, deuterons, tritons and heavy ions, thereby prompting production of the neutrons through non-elastic collisions between the atoms (including the target) in the path of the beam and the particles. The neutron absorbing nuclides absorb neutrons produced in the non-elastic collisions, thereby producing capture products or fragments that irradiate the target volume.SELECTED DRAWING: Figure 1A

Neutron generating targets, for example for use in boron neutron capture therapy ("BNCT"), and methods for manufacturing the neutron generating targets. This specification describes lithium-containing neutron generating targets useful for generating neutron beams for bombarding boron-containing compounds in boron neutron capture therapy of cancer. One method involves pressing a lithium foil against a substrate with sufficient force such that the lithium deforms during the pressing operation and adheres to the substrate, thereby forming a thin lithium layer on the surface of the substrate.

Radiation risks to workers may be high. [Solution] A neutron capture therapy system (100) includes an accelerator (200) for generating a charged particle beam (P), a neutron generator (10) that reacts with the charged particle beam (P) to generate a neutron beam (N), and a beam shaper (20). The beam shaper (20) includes a housing (21), a moderator (22), a reflector (23), a thermal neutron absorber (24), a radiation shield (25), and a beam outlet (26). The housing (21) is provided with a vacuum tube (30) connected to the accelerator (200). The vacuum tube (30) transfers the charged particle beam (P) accelerated by the accelerator (200) to the neutron generator, which can react with the charged particle beam (P) to generate neutrons. The neutron generator (10) moves between a first position and a second position. At the first position, the neutron generator (10) can react with the charged particle beam (P) to generate neutrons. At the second position, the neutron generator (10) detaches from the beam shaper (20).

The utility model belongs to the field of reactor, concretely relates to a kind of space reactor neutron source assembly and reactor system. Wherein space reactor neutron source assembly includes linear moving mechanism and the neutron source rod body of linear moving mechanism output end being arranged, the neutron source rod body includes neutron source functional area, gap and cladding sequentially arranged from inside to outside;The neutron source functional area includes sequentially arranged heat transfer zone, fuel area I, partition area I, neutron source, partition area II and shutdown area. The space reactor neutron source assembly provided by the utility model better utilizes the important position of reactor core center. It can move up and down on the core center, and the structure is simple and compact, efficiently realizes the functions of fuel auxiliary combustion, neutron source start-up, shutdown and reactivity adjustment.

The beam accelerator system includes an ion accelerator for generating an ion beam, a low-pressure chamber, an anode, a plasma window, and a cathode housing. The plasma window includes a plurality of cooling plates. Each cooling plate includes a central wall surrounding an opening, a cooling chamber surrounding the central wall, one or more impingement channels, and one or more return channels. Each of the impingement and return channels enters the cooling plate from an outer edge of the cooling plate and extends toward the opening to the cooling chamber. Each of the one or more impingement channels is configured to provide an inlet path for cooling fluid to enter the cooling chamber, and each of the one or more return channels is configured to provide an outlet path for heated fluid to exit the cooling chamber.

Provided herein are neutron imaging systems (e.g., radiography and tomography) systems and methods that provide, for example, high-quality, high throughput 2D and 3D fast or thermal neutron and / or X-ray images. Such systems and methods find use for the commercial-scale imaging of industrial components. In certain embodiments, provided herein are system comprising a plurality of independent neutron absorber-lined collimators (e.g., 4 or more collimators) extending outwards from a central neutron source assembly.

Systems, devices, and methods for generating orbital confinement fusion reactions are disclosed. The orbital confinement fusion device can include a cathode inner electrode defining a longitudinal axis of the device. The inner electrode can include an emitter material. The orbital confinement fusion device can include an anode outer electrode, the outer electrode coaxial with the longitudinal axis and defining a chamber between the inner and outer electrodes. The orbital confinement fusion device can also include a plurality of magnetic field generators arranged coaxially with respect to the longitudinal axis. The plurality of magnetic field generators can be configured to form a magnetic field within the chamber parallel to the longitudinal axis.

This invention discloses a carbon nanotube cathode ion source device and a neutron tube. The carbon nanotube cathode assembly is disposed at one end of a support pillar, with several protrusions at the end of the assembly furthest from the pillar. A first insulator is fitted onto the outside of the carbon nanotube cathode assembly, and a grid cylinder is fitted onto the outside of the first insulator. Through holes corresponding to the protrusions are formed on the end face of the grid cylinder near the carbon nanotube cathode assembly. A second insulator is fitted onto the outside of the grid cylinder, and a fixing assembly is fitted onto the outside of the support pillar. One end of the fixing assembly abuts against one end of the cathode, the first insulator, the grid cylinder, and the second insulator. An anode cylinder is fitted onto the outside of the second insulator and the fixing assembly. This invention provides a compact ion source structure and improves the degassing temperature, achieving a larger ion current output. It overcomes the disadvantages of complex structures and low degassing temperatures associated with magnetic material components, while also improving the output ion current and enhancing the stability of the ion source operation.

A method for producing a neutrons includes triggering a raising or a lowering of a temperature of a pyroelectric crystal of less than about 40° C. to produce a voltage of negative polarity of at least −100 keV on a surface of a deuterated or tritiated target coupled thereto. A deuterium ion source is pulsed to produce a deuterium ion beam. The accelerating of the deuterium ion beam is achieved by accelerating voltage of the pyroelectric crystal toward the deuterated or tritiated target to produce neutrons. Furthermore, the pyroelectric crystal, the deuterated or tritiated target, and the deuterium ion source are coupled to a common support. The method also includes throwing the common support housing the pyroelectric crystal, the deuterated or tritiated target, and the deuterium ion source near an unknown threat for identification thereof.

A helium-3 detector apparatus generally includes a mass spectrometer having an entry funnel configured to receive (sniff) helium-3 directly from an open environment through an entry port. The entry funnel is configured to direct the helium-3 into the mass spectrometer. The apparatus also includes a heating element configured to release helium-3 from a surface soil layer by means of heat. A movable carrier is configured to position the entry port above the surface soil layer to acquire a sample of helium-3.

The invention discloses a secondary neutron source rod manufacturing process. The secondary neutron source rod manufacturing process comprises the following steps: assembling an inner pipe section; the inner pipe section and the outer shell pipe are assembled, the upper end plug is pressed and plugged into the first end of the outer shell pipe, girth welding is carried out, and then the inner pipe section is installed in the outer shell pipe; installing a lower end plug, pressing and plugging the lower end plug into the second end of the outer cladding tube, and carrying out girth welding; the lower end plug is subjected to helium-filling hole-plugging welding, the outer wrapping shell pipe provided with the lower end plug is installed to a lower end plug helium-filling hole-plugging welding tool, the lower end plug helium-filling hole-plugging welding tool is installed to hole-plugging welding equipment, a welding chamber of the hole-plugging welding equipment is vacuumized, helium with first preset pressure is filled, and helium-filling hole-plugging welding is conducted on the lower end plug. According to the secondary neutron source rod manufacturing process, the flow is simple, the lower end plug is supported and positioned by adopting the lower end plug helium-filling hole-plugging welding tool for helium-filling hole-plugging welding of the lower end plug, the welding efficiency of the lower end plug helium-filling hole-plugging welding can be improved, and the assembling process of a secondary neutron source rod is more convenient.

The present application discloses a compact neutron generator based on an all-glass helicon wave ion source, which belongs to the field of accelerator neutron sources. The neutron generator includes a helicon wave ion source part, a cavity part, and a target part. First, deuterium gas is introduced into the ion source chamber. Then, the deuterium gas is excited by an antenna, thereby generating a helicon wave plasma. Under the constraint of a magnetic field, deuterium ions are first extracted in the form of a beam by the potential difference between an extraction electrode and an ion source cover plate, and then accelerated by the electric field between the extraction electrode and a titanium target. Finally, the deuterium ion beam bombards the titanium target, and a deuterium-deuterium fusion reaction occurs to generate neutrons. At the same time, an arc magnet and a resistor are used to suppress the secondary electrons generated by the target, so as to prevent the secondary electrons from being reversely accelerated and entering the ion source chamber. The present application has the advantages of low energy consumption, a compact structure, high plasma density, autonomous cooling, a good secondary electron suppression effect, high extraction beam intensity, and a high neutron yield.

A neutron imaging system that includes a central neutron source configured to produce source neutrons, wherein the central neutron source comprises a beam target, a moderator chamber surrounding at least a portion of the beam target, the moderator chamber housing a moderator, and a re-entrant cone extending into the moderator chamber. The re-entrant cone includes an entrance surface facing the beam target. The entrance surface encloses a cone chamber, isolating the cone chamber from the moderator. Furthermore, the entrance surface is shaped such that source neutrons produced at the beam target impinge the entrance surface with a neutron flux that varies by 10% or less along the entrance surface.

Methods and systems for exposing a patient to a neutron beam according to a treatment plan for treating a tumor in the patient using boron neutron capture therapy (NCT) are disclosed.

A neutron capture therapy system and a target for a particle beam generating device, which may improve the heat dissipation performance of the target, reduce blistering and extend the service life of the target. The neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron generating device includes an accelerator and a target, and a charged particle beam generated by acceleration of the accelerator interacts with the target to generate a neutron beam. The target includes an acting layer, a backing layer and a heat dissipating layer, the acting layer interacts with the charged particle beam to generate the neutron beam, the base layer supports the action layer, and the heat dissipating layer includes a tubular member composed of tubes arranged side by side.

The invention provides a modularized isotope production system and method based on a D-T neutron source, the modularized isotope production system based on the D-T neutron source adopts a D-T neutron source module to generate a D + ion beam to react with a tritium target to generate neutrons, and then the neutrons irradiate an irradiation target material to produce isotopes. The system is high in isotope production efficiency, free of fission products and low in post-treatment cost.