315results about "Direct voltage accelerators" patented technology

The invention relates to the technical field of isotope production, in particular to a welding-free target capsule for isotope production and a manufacturing method of the welding-free target capsule. The welding-free target capsule comprises a target material used for generating isotopes under bombardment of high-energy particles; the first metal film covers one side of the target material; the second metal film covers the other side of the target material; wherein the first metal film and the second metal film are made of materials with ductility; the edge of the first metal film and the edge of the second metal film are attached to each other on the peripheral side of the target material and are folded into an annular sealing structure. In the invention, the metal film with good ductility is used as a coating material of the target material, and the sealing structure is formed by folding the connecting part of the metal film, so that the target capsule can be ensured to efficiently dissipate heat in a water-cooling environment, the manufacturing mode of the sealing structure can be improved, the manufacturing steps of the sealing structure are simple and easy to implement, and the manufacturing cost of the target capsule is further reduced.

The invention relates to the technical field of yield control, in particular to a neutron generator yield control method and system. The method comprises the following steps: establishing a polynomial model by using historical yield data to predict a target efficiency attenuation factor; dynamically determining neutron event boundaries in the pulse integral value and the pulse width two-dimensional characteristics based on the attenuation factor, and counting the neutron event boundaries; the yield deviation and the change rate are calculated, and when the deviation exceeds a threshold value, feedforward compensation is carried out on the target yield; and selecting a three-dimensional lookup table, an input deviation, a change rate and a current high voltage according to the interval to which the attenuation factor belongs, and cooperatively determining the adjustment amount of the ion source current and the accelerator high voltage. According to the scheme, the measurement and control problems caused by aging of the target piece can be solved, and the precision, the response speed and the long-term stability of yield control are improved.

The invention discloses a gas target device for isotope production, and the gas target device comprises a seat body which is provided with a channel; the water-cooled jacket body is mounted on the seat body, and the water-cooled jacket body is provided with a water-cooled cavity for circulating a water-cooled medium; the target body is installed on the base body and comprises a target body, the target body is located in the water cooling cavity and is provided with a target cavity, and the target cavity, the channel and the accelerator beam leading-out port are sequentially arranged in the set direction. According to the gas target device for isotope production disclosed by the embodiment of the invention, the water-cooled jacket body is arranged for cooling the target body, so that the target body is prevented from being damaged due to overhigh temperature of the target gas, the target gas can receive beam irradiation with higher flow intensity, and the isotope yield is improved.

The invention relates to the technical field of data processing, and discloses a digital feedback dynamic adjustment method and system for a neutron generator control signal, and the method comprises the steps: calling a reconfigurable waveform parameter set corresponding to a target neutron from a mapping relation according to the yield and beam spot characteristic demands of the target neutron; generating a basic high-frequency pulse sequence of the neutron tube, and performing pre-distortion filtering on the basic high-frequency pulse sequence to obtain a high-frequency pulse sequence of the neutron tube; collecting an anode current and a target voltage signal of the neutron tube applied with the high-frequency pulse sequence during operation, and converting the anode current and the target voltage signal into a digital feedback current; comparing the digital feedback flow with a reference waveform in the reconfigurable waveform parameter set in real time to obtain an error correction amount of the high-frequency pulse sequence; dynamically adjusting the high-frequency pulse sequence according to the error correction; applying the dynamically adjusted high-frequency pulse sequence to a corresponding electrode in a neutron tube through power; the neutron tube control signal processing efficiency can be improved.

The invention discloses a method for efficiently generating high-brightness gamma radiation, and belongs to the technical field of radiation. A relativistic electron beam is injected into the porous microstructure foam target material, and high-brightness gamma ray radiation is generated. According to the method, the used device is simple, only the single relativistic electron beam and the porous microstructure foam target material are needed to interact, compared with a traditional uniform-density solid material, the energy conversion efficiency in the interaction process of the electron beam and a substance can be remarkably improved, and the energy conversion efficiency can be remarkably improved through the effective constraint effect of a high-intensity magnetic field. And the problems of low energy conversion rate, low light source brightness, poor radiation directivity, complex device or difficulty in experiment implementation and the like of the existing high-energy gamma ray radiation source are solved.

A radiation device comprises at least a vacuum chamber (1), an electromagnetic accelerator (8) for generating a primary energy beam of ions inside the vacuum chamber (1), and a layer of material (S) carried by a support (4) rotating in the vacuum chamber (1) to generate a flow of particles when a series of nuclear fusion reactions are triggered on the material (S) thanks to the energy of said beam, and wherein the support (4) is hollow and sealed defining a rotating three-dimensional surface that surrounds a containment volume for a cooling liquid in heat exchange with the layer of material (S), such rotating three-dimensional surface defining a heat exchange surface wetted by the liquid, and wherein a level of the free surface of the liquid on the heat exchange surface moves upwards in use due to the action of the centrifugal acceleration generated by the rotation of the support (4).

A hinge mechanism includes a hinge base and rotating support mechanisms respectively connected to two opposite sides of the hinge base. The rotating support mechanism includes a rotating shaft, a hinge rotating plate and a hinge moving plate. The hinge rotating plate is rotatably connected to the hinge base through the rotating shaft, has a first end adjacent to the rotating shaft and provided with an accommodating groove. The rotating shaft has a speed reducer with a rotating output portion which can rotate along with the rotating shaft. A rotating speed of the rotating output portion is lower than that of the rotating shaft, and the rotating output portion and the hinge moving plate are rotatably connected to each other. The hinge moving plate includes a second support portion, and the second support portion is at least partially located in the accommodating groove.

The invention provides a rotating target for generating monoenergetic neutrons, which comprises a target chamber, a target sheet, a sealing flange and a vacuum system, the target sheet is composed of a TiD / TiT target material and a substrate, a deviation distance of 5-10mm exists between the center of the target material and the center of the substrate, the substrate is connected with a motor outside the target chamber through a fixed connecting rod, and the target chamber is driven by the motor to rotate at a speed of 3-5min / r. The target material is designed to be the eccentric target rotating slowly, so that the utilization rate of the target material can be improved, and the phenomena that the temperature of a single point is too high, a coating layer penetrates or falls off, enriched gas escapes and neutron yield fluctuation is caused due to the fact that beam bombards one position of the target material for a long time can be avoided. The energy width of neutrons generated by the rotating target is lower than 5%, the rotating target has good monochromaticity and low energy loss, the design precision requirement of the fourth-generation nuclear reactor can be met, and a possible guarantee is provided for commercialized popularization and application of the fourth-generation nuclear reactor.

The invention discloses an accelerator neutron source solid-state lithium target cooling device, and relates to the technical field of accelerator neutron source medical application. An annular heat pipe is arranged on the outer ring of the side portion of an oxygen-free copper substrate, a plurality of liquid absorption cores are arranged on the inner wall of the heat pipe, and meanwhile an inner cavity of the heat pipe is filled with a working medium; when heat is generated, the heat is firstly transferred to the oxygen-free copper substrate, the evaporation section of the heat pipe is heated, the working medium in the wick is quickly evaporated and gasified, the generated steam flows to the condensation section under the driving of differential pressure and is condensed into liquid in the condensation section and releases heat, and the liquid generated by condensation returns to the evaporation section again under the capillary action of the wick. The space of the arranged heat pipe is large, and in the aspect of heat dissipation, the working medium is subjected to gas-liquid phase change in the heat pipe under the action of the liquid absorption core, so that the accelerator is rapidly dissipated, heat on the solid target material film can be rapidly taken away, and the cooling effect on the accelerator is greatly improved.

This invention discloses a conveniently detachable, actively water-cooled solid-state deuterium target based on a compact neutron source, comprising a micron-sized solid titanium film, a titanium film carrier, and a water-cooled substrate. Deuterium is deposited in the solid titanium film by bombarding it with a deuterium ion beam, and neutrons are generated by collisions with the subsequent deuterium ion beam. Oxygen-free copper, with its high thermal conductivity, is used as the carrier for the titanium film. The threaded structure on the side of the titanium film carrier allows for convenient installation and removal from the water-cooled substrate. The oxygen-free copper substrate, with multiple annular water-cooling structures inside, enables rapid and effective removal of heat flux from the target, preventing deuterium particles deposited in the solid titanium film from desorbing due to excessive temperature, thus avoiding impact on neutron yield. This invention provides a conveniently detachable, actively water-cooled solid-state deuterium target suitable for compact deuterium-deuterium neutron generators, providing a sound technical foundation for the widespread application of compact accelerator neutron source systems in production and daily life.

A rotating target high yield compact D-D neutron generator disclosed by the present invention comprises an ion source unit, a vacuum main body unit and a target unit, the ion source unit generates a deuterium ion beam, the deuterium ion beam is introduced into a vacuum chamber and passes through a leading-out accelerating electrode for acceleration, and the accelerated deuterium ion beam bombards the circumferential target surface of a molybdenum target to generate a deuterium ion beam. And deuterium-deuterium fusion reaction with deuterium nuclei injected into the molybdenum target in advance is carried out, fast neutrons are released, and the neutron yield is improved. The rotating driver of the target unit drives the molybdenum target of the cylindrical structure to rotate through the insulating rotating shaft, the molybdenum target rotates to distribute beam power to the circumferential target surface of the molybdenum target, a cooling medium is conveyed to one side of the inner side wall of the molybdenum target in combination with the cooling channel, the molybdenum target is cooled, and the service life of the target unit can be effectively prolonged. The leading-out accelerating electrode is located in the vacuum cavity, operation of the vacuum main body unit is not affected by external humidity and temperature environment conditions, high-voltage ignition discharge can be effectively restrained, and the safety performance of a high-voltage electric field is improved.

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.

A dual-radionuclide production target includes a first radionuclide target that produces a first radionuclide when irradiated by a particle beam from a radionuclide production system, and a second radionuclide target that produces a second radionuclide when irradiated by the particle beam that has passed through, and been degraded by, the first radionuclide target. With this design, the first radionuclide target serves two purposes: it reduces the beam energy to a suitable energy for isotope production on the second radionuclide target, and in-doing so becomes activated with a medically relevant radionuclide that can be easily extracted. In this way, in a single production run can produce two or more radionuclides.

The invention discloses a device for assisting installation and calibration of main parts of a serial accelerator, and relates to the technical field of installation and calibration, the device comprises a first base, the top of the first base is fixedly connected with a track, the top of the track is provided with a plurality of second bases, the tops of the second bases are provided with assembling assemblies, and the assembling assemblies are internally provided with accelerators. A first accelerating tube, a second accelerating tube, an adapter flange and a corrugated tube are arranged in the accelerator, and a driving assembly is arranged at the top of the second base; the assembly assembly includes a support ring. The first clamping plate and the second clamping plate can be attached to the outer wall of the accelerator all the time, the first clamping plate and the second clamping plate are connected and limited through the rubber plate, the rubber plate can be well attached to the outer wall of the accelerator in a deformation mode, and the effects of self-centering of the accelerating tube and convenient rotary installation are achieved; the problem that calibration is tedious due to the fact that a plurality of tools need to be used in cooperation is solved, and accelerator installation convenience is improved.

The invention relates to the technical field of engineering logging, and discloses a low-power-consumption radio frequency ion source logging neutron tube and a working method, deuterium gas is ionized into deuterium ions through an ion source, the deuterium ions are accelerated under the action of a strong electric field to obtain energy, and the high-energy deuterium ions bombard a deuterium / tritium target to generate nuclear reaction to generate neutrons. The power requirement of the radio frequency source can be greatly reduced. Compared with an inductive coupling type radio frequency ion source neutron tube, the capacitive coupling type neutron tube has the advantages that D1 + 1 in plasma is increased to 50%, the required power is 25%-30% of that of the inductive coupling type neutron tube, the load of a neutron generator is greatly reduced, the D-D deuterium neutron tube is further applied to engineering practice, and powerful technical support is provided for green and environment-friendly well logging.

The present application relates to the technical field of neutron source, and particularly provides a high-heat-carrying neutron target system, which aims to solve the problem of poor heat dissipation capacity of the neutron target system. To this end, the high-heat-carrying neutron target system comprises a base and a jet cylinder, the base comprises a first end portion and a second end portion; the jet cylinder is wrapped on the outer side of the base; and the high-heat-carrying neutron target system further comprises a turbulence structure, the turbulence structure comprises a first heat dissipation structure and a second heat dissipation structure for flowing cooling medium, the first heat dissipation structure is arranged on the base and penetrates through the base in the direction from the first end portion to the second end portion; and the second heat dissipation structure is arranged on the jet cylinder, the second heat dissipation structure is communicated with the first heat dissipation structure, and the cooling medium in the second heat dissipation structure flows into the first heat dissipation structure in a preset direction to form turbulence for the cooling medium in the first heat dissipation structure. In the present application, the second heat dissipation structure is used to effectively increase the turbulence degree of the cooling medium in the first heat dissipation structure, thereby greatly improving the heat exchange effect of the neutron target system.

Provided herein are high energy ion beam generator systems and methods that provide low cost, high performance, robust, consistent, uniform, low gas consumption and high current / high-moderate voltage generation of neutrons and protons. Such systems and methods find use for the commercial-scale generation of neutrons and protons for a wide variety of research, medical, security, and industrial processes.

An in-situ cartridge comprises a substrate for holding a sample wherein said substrate comprises an electron transparent window for receiving said sample and at least one optical waveguide for illuminating said sample wherein a first edge of the at least one optical waveguide is optically couplable with a light source, wherein the at least one optical waveguide is integrated in the substrate and is extended from an edge of the substrate towards the electron transparent window. In this configuration, only the substrate carrying the sample needs to be modified. Bringing the optical waveguide in the vicinity of the sample allows for various additional light sensing techniques, as well as heating and application of electric fields.

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.

An irradiation station for producing a radioisotope, having a cyclotron (32) for emitting a proton beam (B) against a solid target material (M) placed in a container (1) and a cooling system (33) for cooling the container (1). The container (1) has a wall (4) for supporting the solid target material (M) and a cavity (12), which borders the wall (4) and has an opening (14) transverse to the axis of the container (1). The cooling system (33) has a connection head (34) which is couplable to the opening (14) for circulating a cooling fluid in the cavity (12) and comprises a flow diverter (37), a tip (47) protruding from a hole (46) of the flow diverter (37) and movable along the hole (46) against the action of a spring (48) in contact with the tip (47), and an electrical connector (52) in contact with the spring (48). When the connection head (34) is coupled to the opening (14) the flow diverter (37) enters the cavity (12) coaxially with the container (1) and the tip (47) presses against the wall (4).

The utility model provides a BNCT neutron target system, which comprises a continuous band-shaped functional assembly, a continuous band-shaped active layer and a continuous bearing layer, the continuous band-shaped functional assembly comprises a continuous or intermittent band-shaped active layer and the continuous bearing layer is used for bearing the active layer, and the continuous band-shaped active layer comprises a continuous band-shaped active layer and a continuous band-shaped active layer. One end of the functional assembly is mounted on the unwinding assembly, the other end of the functional assembly is mounted on the winding assembly, and a working area is formed between the unwinding assembly and the winding assembly; the intercepting assembly has the width and the length which are not smaller than those of the working area, the intercepting assembly comprises a heat dissipation layer and a hydrogen storage layer which are arranged in a mutual contact mode, and the hydrogen storage layer is arranged opposite to one side of the bearing layer in the functional assembly and makes contact with the bearing layer in a non-fixed mode. The utility model solves the problems that the service life of the conventional fixed BNCT neutron target material is short, and the target material is scrapped due to the separation of an action layer caused by the defects of bubbling and the like in the use process.

Systems, devices, and methods for converting a raw neutron beam to a specified deliverable format having a targeted energy range, size, and direction are described. Embodiments of a neutron beam converter can include numerous regions based on location, function, dimension, and / or constituent material. The regions can include a central region, an intermediate region, a peripheral region, and a frontal region. Materials are also described.

The present disclosure provides a neutron target device for boron neutron capture therapy, comprising: a container having a containing cavity; a neutron target component arranged in the containing cavity, the neutron target component comprising a target disc and a target sheet detachably connected with the target disc; a rotating component connected with the target disc for driving the neutron target component to rotate; a driving component connected with the rotating component for driving the rotating component to rotate; and a cooling component arranged at an end of the rotating component away from the neutron target component for supplying a cooling liquid; wherein the rotating component is provided with a liquid inlet cavity and a liquid outlet cavity, the target disc is provided with a liquid inlet flow channel and a liquid outlet flow channel, and the target sheet is provided with a liquid inlet hole and a liquid outlet hole; the liquid inlet flow channel is in communication with the liquid inlet cavity and the liquid inlet hole, and the liquid outlet flow channel is in communication with the liquid outlet cavity and the liquid outlet hole. The flow path structure of the neutron target device of the present disclosure is conducive to improving the cooling rate of the target sheet; and the target sheet is detachably connected with the target disc, which is conducive to the convenience of replacing the target sheet.

The present application relates to the technical field of isotope production equipment, and particularly relates to a target capsule facilitating replacement of target material and a target material replacement method. The target capsule comprises: a first shell provided with a first recess, the opening of the first recess being located at the first end face of the first shell; a second shell provided with a second recess, the opening of the second recess being located at the first end face of the second shell; and a target material for receiving bombardment of high-energy particles to generate isotopes; wherein the first shell is embedded in the second recess and is threadedly connected with the second shell, the target material is installed in the first recess, and the bottom wall of the second recess covers the opening of the first recess. In the present application, the sealing structure of the target capsule is optimized to be the first shell and the second shell connected through a threaded structure, so that workers can conveniently assemble, disassemble and replace the target material of the target capsule, the sealing structure can be repeatedly used, and the production efficiency of isotopes is improved.

To provide an ion source and an accelerator, as well as a method for generating ions and accelerating those ions in the ion source.SOLUTION: A nuclear reaction generation device includes a chamber configured to contain gas and include a target. The nuclear reaction generation device also includes a filament provided within the chamber and a voltage source configured to apply a first positive voltage to the filament relative to the chamber. The first positive voltage is configured to heat the filament to a temperature that causes thermionic emission and generates multiple thermions. The multiple thermions are configured to ionize the gas and generate positive ions in the chamber. The target is configured such that nuclear reactions occur when the positive ions interact with the target.SELECTED DRAWING: Figure 1

The present disclosure relates to a low-stress thin film comprising a number of bilayers, wherein a bilayer comprises a first layer comprising M, and a second layer comprising X; and wherein at least one of the first layer and the second layer comprises at least one of 11B4C, 10B4C, B4C, 11B, 10B, B and C. The present disclosure 5 also relates to use and a method of producing said low-stress thin film.

The invention discloses a high-thermal-conductivity solid target, which belongs to the technical field of accelerator neutron sources and comprises an insulating PEEK base and an integrated solid target. The integrated solid target is arranged on the insulating PEEK base, and a target body of the integrated solid target is tightly attached and fixed to the insulating PEEK base; a circular positioning groove is formed in the insulation PEEK base and used for fixing the initial position of the integrated solid target, a sealing ring clamping groove is formed in the circular positioning groove, and two water cooling channels are arranged in a base body below the positioning groove in a penetrating mode. The back of the target body of the integrated solid target is integrated with a plurality of groups of radiating fins and an inverted-cone-shaped groove right facing a deuterium beam, so that an efficient radiating channel is formed. According to the high-thermal-conductivity solid target, by arranging the inverted-cone-shaped grooves and the cooling fins, the heat exchange area of beams can be increased, the structural stability of the high-thermal-conductivity solid target can be enhanced, the thermal stress level can be reduced, and the structural integrity and long-term working reliability of the target material can be guaranteed.

The invention discloses a method for realizing an ultra-compact self-moderation neutron generator. The ultra-compact self-moderation neutron generator comprises an ion source system, a vacuum system and a target system, according to the method, a high-voltage base is introduced into the ultra-compact self-moderation neutron generator, and the high-voltage base is fixedly connected with a target base of the target system. According to the ultra-compact self-moderation neutron generator, by introducing the high-pressure base made of the polyethylene material, on one hand, the device has the neutron moderation capacity, and the requirement of the outside for neutron moderation is lowered; on the other hand, the high-pressure base directly participates in vacuum sealing, so that the device is more compact The shielding layer structure plays a role in preventing neutrons from diffusing all around. The device has the advantages of small overall size, high integration level, high moderation efficiency, high neutron utilization rate and the like.

The invention relates to a nested high-voltage generator and a high-voltage generation method thereof. The nested high-voltage generator comprises an independent sub-power supply, a capacitor, an electrode plate and a conductive shell, the independent sub-power supply is connected in series with the electrode plate and connected in parallel with the capacitor to form a high-voltage generating circuit; the conductive shell surrounds the outer side of the high-voltage generating circuit to form a Faraday cage, and the independent sub power supply and the capacitor are arranged in the conductive shell; a plurality of Faraday cages exist, the plurality of Faraday cages are nested, and the Faraday cage nested in the inner layer is placed in the conductive shell nested in the Faraday cage nested in the outer layer; the independent sub-power supply of the nested inner layer is connected in series with the independent power supply of the nested outer layer, and the capacitor of the nested inner layer is connected in series with the capacitor of the nested outer layer. The nested high-voltage generating circuit is provided with a plurality of independent sub-power supplies, each independent sub-power supply can independently supply power, when any one of the independent sub-power supplies is damaged, the other high-voltage generating circuits can work independently, normal use is not affected, and the technical effect of reducing regular maintenance cost and repair cost of the high-voltage generator is achieved.