134results about "Neutron sources" patented technology

Techniques are described for producing actinium-225 by arranging a converter material at least partially around a target material, where the target material includes radium-226. The converter material comprises a compound of lithium and hydrogen at least partially enriched with lithium-6 and deuterium, and is configured to convert thermal neutrons to fast neutrons, which are then incident on the radium-226. If the fast neutrons have a kinetic energy of at least 6.4 MeV, they will initiate a (n,2n) reaction that converts radium-226 into radium-225, which then decays into actinium-225. The process can desirably be performed within an environment rich in thermal neutrons, such as within a fission reactor.

The invention belongs to the technical field of nuclear physics and particle accelerators, and relates to a high-precision wide-energy-spectrum neutron source target body structure applied to a spallation neutron source device. The method comprises the following steps: a tungsten target is adopted, and a 6cm thin target design is adopted; the cooling layer contains boron water and the like and can be used for cooling and slowing down neutrons; the moderation layer moderates the neutron energy spectrum to a thermal neutron energy region by using boron-containing water; the shielding layer is made of low-carbon steel and concrete to ensure radiation safety; the tail end of the neutron channel is connected with an experimental terminal; according to the thin target design, the energy resolution is improved, the energy resolution of neutrons below 100 keV is higher than 0.1%, and the energy resolution of neutrons below 1 MeV reaches 0.3%; the boron element reduces the gamma ray background; and the five neutron pore channels meet various requirements. The overall design realizes the effect required by the high-precision neutron experiment and improves the precision of the device.

The invention discloses a detection control device, a detection control method and a petroleum logging neutron tube system. The detection control device comprises a radio frequency power supply, an impedance matching module, a filtering module, a current detection module and a control module, the radio frequency power supply is used for providing radio frequency energy for the radio frequency electrode, so that working gas in an ion source in the neutron generator generates plasma; the current detection module is used for providing direct current voltage for the radio frequency electrode and detecting information of direct current flowing through the radio frequency electrode; the filtering module is used for preventing radio frequency energy from entering the current detection module and preventing direct current from entering the radio frequency power supply; the control module is used for controlling the output power of the radio frequency power supply according to the direct current information. According to the detection control device, the detection control method and the petroleum logging neutron tube system, the density of plasma in the neutron generator can be obtained in real time, a stable and reliable feedback signal is provided for output power control of a radio frequency power supply, and the stability of neutron output is ensured.

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 present invention relates to the technical field of target containers in boron neutron capture therapy technology, particularly to a cylindrical target container; the target container includes a container housing, a rotating target, a rotating sealing ring, a transmission device, a liquid collecting tank, an evaporation crucible, a cleaning assembly, a sealing door, and a film thickness gauge; the container housing, the liquid collecting tank, and the sealing door form a container cavity; the rotating target includes a cylindrical target and a rotating shaft; the rotating target is connected to the container housing through the rotating sealing ring; the sealing door is installed at the opening of the container cavity; the cylindrical target is arranged inside the container cavity; the cylindrical target includes a flow guiding plate and a surface substrate; the flow guiding plate is arranged inside the cylindrical target; the surface substrate is arranged on the outer side surface of the cylindrical target. The flow guiding plate and the surface substrate form a heat exchange channel; using this target container can achieve functional integration, non-contact automatic target material replacement, reduce the target material replacement frequency, improve the heat exchange efficiency of the target, save space, and have a self-cleaning function.

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.

The present invention relates to a y-type inclined lithium target for generating high power neutrons, comprising a pair of target modules comprising a substrate extending to a predetermined width and a solid target provided on one surface of the substrate, wherein the pair of target modules are installed at a first angle with respect to each other and are disposed at a second angle with respect to a direction in which a particle beam is irradiated. The y-type inclined lithium target for generating high power neutrons according to the present invention has the advantage of being capable of maximizing a heat transfer area. In addition, since the target is configured as a pair of target modules, each of the target modules can be miniaturized. Accordingly, generation and accuracy of a lithium layer can be improved, and the advantage of easy storage is provided.

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.

The utility model discloses a self-shielding neutron target device and a self-shielding neutron target system, the self-shielding neutron target device comprises a neutron target and a shielding housing, the neutron target comprises a target disc and a rotating part, the target disc is connected with the rotating part, the shielding housing is provided with a shielding chamber and a channel, the shielding chamber is used for packaging the target disc, and the rotating part passes through the channel. The shielding shell is further provided with a connecting end and an emitting end, the connecting end faces at least one part of the target disc, and the emitting end and the connecting end are located on the two opposite sides of the target disc. The shielding cavity can effectively package the target disc, generated neutrons and other radiation are limited in the shielding cavity, radiation leakage is avoided, the neutron target equipment is protected, operators can be prevented from being hurt by radiation, a channel for the rotating part to penetrate out is reserved in the shielding shell, and movement of the rotating part cannot be hindered while the sealing effect is achieved.

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.

Techniques are described for producing radium-225 from a sample containing radium- 226, and milking the sample for actinium- 225, which results in a higher yield of actinium-225 for a given sample in a given period of time compared with conventional approaches. In particular, returning the sample to the reactor while there is still a significant amount of radium-225 in the sample can, over time, produce more actinium- 225 than the conventional approach of milking the sample until the vast majority of radium-225 has decayed into actinium-225.

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.

A neutron beam source generation system, a neutron beam source stabilization control system, and a neutron beam source generation method are provided. The neutron beam source generation system includes an accelerator, a target, and a calibration module. The accelerator is configured to generate a proton beam. A neutron beam source is generated by irradiating the target with the proton beam. The calibration module includes a pair of electromagnet components, a profile-measuring component, a current-measuring component, and a Faraday cup component. The calibration module uses the pair of electromagnet components to control the distribution of the proton beam according to the profile distribution of the proton beam as measured by the profile-measuring component. The calibration module adjusts the current of the proton beam according to the first current value as measured by the current-measuring component, the second current value as measured by the Faraday cup component, or both.

The utility model provides a neutron beam moderation system and an accelerator neutron source platform, and relates to the technical field of neutron sources. The neutron beam moderation system comprises a moderation module, a first liquid storage device and a second liquid storage device. Wherein the moderation module is provided with at least two cavities used for containing moderation liquid, and the cavities are arranged in parallel; the first liquid storage device is blocked or communicated with the cavity and used for storing the moderation liquid to enter the cavity. And the second liquid storage device is blocked or communicated with the cavity and is used for storing the moderation liquid discharged from the cavity. And the moderation liquid is discharged into the cavity through the first liquid storage device, and the moderation liquid discharged from the cavity is received through the second liquid storage device. In this way, by changing the number of the cavities filled with the moderation liquid, the moderation system achieves different moderation effects. Furthermore, neutron beams with different energy spectrums can be generated through the moderation system, so that a moderation scheme capable of changing the energy spectrums of the neutron beams is provided for a miniaturized accelerator.

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.

A system and method is disclosed for detecting fissionable materials. In one embodiment the system may incorporate a neutron pulse generator configured to generate multiple short pulses of neutrons, or a single pulse of sufficient intensity, in a vicinity of an object of interest. The source pulse of neutrons includes neutrons which each have a full width half maximum time duration of less than about 100 ns and a peak energy level no greater than about 20 MeV. A fast response detector is used which is able to detect single neutron events indicative of fission neutrons having been produced by the source pulse of neutrons interacting with fissionable material associated with the object of interest, and which arrive at the fast response detector within a predetermined time window immediately before arrival of the source neutron pulses.

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.

A plasma focus system for neutron production is disclosed that includes a plasma focus device and a neutron source. The plasma focus device is configured to emit a remnant ion beam. The neutron source includes an enclosure having a cavity formed therein for receiving a target medium. Depending on the application, the target medium can be a gas, a liquid, or a solid. The enclosure includes a beam entrance port configured to allow at least part of the remnant ion beam to enter and travel inside the cavity. As the remnant ion beam travels along the cavity, the beam ions interact with the target medium and undergo both fusion collisions and non-fusion collisions. The fusion collisions produce neutrons and reduce a number of the beam ions, while the non-fusion collisions reduce an energy of the beam ions. A plasma focus method of neutron production is also disclosed.