457results 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 a closed circulation 226Ra solution target system for producing 225Ac. The closed circulation 226Ra solution target system comprises a solution type 226Ra target, an isotope target bin, a valve, a 226Ra solution circulation structure, a radium actinide separation structure, a radium lead separation structure, a photon detection system I, a photon detection system II, a heat exchange system, a pressure reduction radon evaporator and a radon treatment system, and the solution type 226Ra target comprises a solution circulation pipeline and a radium-containing solution. The radium-containing solution is contained in the closed solution circulating pipeline; the solution circulating pipeline comprises a main loop pipeline and two branch pipelines; the photon detection system I, the 226Ra solution circulation structure, the pressure reduction radon evaporator, the heat exchange system, the valve and the photon detection system II are sequentially arranged on the main loop pipeline; and the radium actinide separation structure and the radium lead separation structure are respectively arranged on the two branch pipelines. The system can improve the preparation efficiency and yield of 225Ac.

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 relates to the technical field of neutron therapy and discloses a neutron therapy system based on multiple neutron tubes, the neutron therapy system based on multiple neutron tubes comprises n neutron tubes and a regulation and control module, the regulation and control module is provided with n mounting blind holes arranged at intervals, and the central axes of the mounting blind holes intersect at a first point, the first point and the regulation and control module are arranged at an interval, the neutron tubes extend into the mounting blind holes, outlets of the neutron tubes abut against the bottom surfaces of the mounting blind holes, the neutron tubes correspond to the mounting blind holes in a one-to-one mode, and the regulation and control module can regulate and control neutrons emitted by the neutron tubes so that the flux of the neutrons and the energy of the neutrons can meet the requirements of neutron treatment. According to the neutron therapy system based on the multiple neutron tubes, the technical problem that the size of the neutron therapy system is large can be solved, the n neutron tubes are installed on the regulation and control module, and the regulation and control module can regulate and control neutrons emitted by the neutron tubes, so that the flux and energy of the neutrons meet the requirements of neutron therapy.

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 present invention relates to a device-produced medical isotope 225 Photonuclear reaction preparation in Ac production technology 225 Ac radium target design, specifically involving a method for producing 225 Ac's 226 Ra isotope target and its application. 226 The Ra isotope target comprises a nickel substrate, 226 Ra isotope sample, nickel electroplating layer and nickel protective shell; wherein, 226 The Ra isotope sample is evenly concentrated in the center of the nickel substrate, and the nickel electroplating layer covers 226 The outer surface of the Ra isotope sample, and the nickel substrate and nickel electroplating layer will 226 The Ra isotope sample is wrapped in the middle; the nickel protective shell wraps the nickel electroplating layer. 226 Ra isotope targets can be used in electron linear accelerators as a photonuclear reaction production 225 Ac raw material target, can improve 225 Production of Ac isotopes.

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 present invention relates to a production 225 Closed cycle of Ac 226 Ra solution target system. The closed cycle 226 Ra solution target system includes solution type 226 Ra target, isotope target chamber, valve, 226 Ra solution circulation structure, radium-actinium separation structure, radium-lead separation structure, photon detection system I, photon detection system II, heat exchange system, vacuum radon evaporator and radon treatment system, among which, solution type 226 The Ra target includes a solution circulation pipeline and a radium-containing solution, and the radium-containing solution is contained in a closed solution circulation pipeline; the solution circulation pipeline includes a main loop pipeline and two branch pipelines; the photon detection system I, 226 The Ra solution circulation structure, vacuum radon evaporator, heat exchange system, valve and photon detection system II are sequentially arranged on the main loop pipeline; the radium-actinium separation structure and the radium-lead separation structure are respectively arranged on the two branch pipelines. 225 Preparation efficiency and yield of Ac.

The present invention relates to the technical field of isotope production equipment and provides a target device for isotope production based on a high-current particle accelerator, comprising: a target chamber and a target assembly; the target chamber having an inner cavity and a side facing the beam having a plurality of beam holes arranged in an array, the beam holes being covered with target windows; the target assembly comprising a target frame; the target frames being arranged in a one-to-one correspondence with the target windows, and at least one mounting position for a target capsule being provided in the target frame in the axial direction of the beam holes; openings being provided on both sides of the target frame, and a plurality of target frames arranged in a preset direction forming a group; the side openings of the target frames in the same group corresponding to each other and forming independent coolant flow channels with the inner wall of the target chamber; each target capsule having a gap on both sides along the axial direction of the beam hole for coolant to flow through; and a plurality of water inlet holes and water outlet holes corresponding to the plurality of coolant flow channels being provided on both sides of the target chamber. This arrangement can effectively reduce the temperature rise of the target material under high beam intensities, enabling isotope production at beam intensities above the milliampere level.

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.

The utility model discloses a spin coating target and an accelerator with the spin coating target, and the spin coating target comprises a shell which is provided with a vacuum cavity; the target base body is rotatably arranged in the vacuum cavity, and an annular coating area is defined on one side of the target base body; the liquid target material is used for coating the coating area so as to enable the coating area to form a target surface which can be bombarded by a set beam to generate neutrons; at least one part of the coating device is arranged in the vacuum cavity, and the coating device is used for coating the coating area with the liquid target material; and the at least one cooling device is arranged close to the target base body to cool the target surface. According to the spin-coating target disclosed by the embodiment of the utility model, the spin-coating device is arranged to coat lithium on the coating area, so that the problem that the service life of a rotary lithium target is short under the condition that the power density of a proton accelerator is very large can be solved, the supply of lithium on the target surface can be maintained, and the service life of the spin-coating target can be prolonged.

The invention belongs to the technical field of medical equipment, and particularly relates to an accelerator-based detachable sealed water-cooling solid-state lithium target which comprises a lithium target body, the lithium target body comprises a target seat assembly and a target disc assembly, the target seat assembly comprises a target seat body, the target seat body is of a cylindrical structure, a cooling plate is arranged at the bottom end of the target seat body, and a cooling water channel groove is formed in the upper surface of the cooling plate; the side wall of the cooling plate is provided with a water inlet joint and a water outlet joint which are respectively connected with two ends of the cooling water channel groove; the target disc assembly comprises a target disc body, the target disc body is clamped in the target seat body, the target disc body is of a cylindrical structure, a copper substrate is horizontally and fixedly arranged in the target disc body, a lithium layer is arranged on the upper surface of the copper substrate, an annular connecting plate is arranged on the outer side wall of the top end of the target disc body, and the connecting plate is detachably and fixedly connected with the top end of the target seat body. The target seat assembly and the target disc assembly are of a split structure and are connected through the connecting plate, the target disc assembly can be detached from the target seat assembly during replacement, the workload of replacement operation is reduced, the working efficiency is improved, and meanwhile the replacement cost is reduced.

The utility model provides a rotary neutron target. The rotary neutron target comprises a neutron generation layer, a hydrogen diffusion layer and a cooling device, the cooling device comprises a cooling substrate and a rotating shaft, the cross section of the cooling substrate is circular, and the rotating shaft is vertically and fixedly connected to the circle center of the cooling substrate; the cross sections of the neutron generation layer and the hydrogen diffusion layer are of a first annular structure and a second annular structure respectively, and the first annular structure and the second annular structure are the same in shape and area. The hydrogen diffusion layer, the neutron generation layer and the cooling substrate are coaxially arranged, the hydrogen diffusion layer is arranged above the cooling substrate, and the neutron generation layer completely covers the hydrogen diffusion layer. According to the structure, all protons enter the hydrogen diffusion layer, and heat generated by the neutron generation layer and the hydrogen diffusion layer on the rotating neutron target is rapidly taken away, so that the heat is uniformly distributed, and high temperature of the target material caused by proton aggregation is avoided; according to the structure, proton energy deposition is basically in the hydrogen diffusion layer, the neutron generation layer is effectively protected, and the service life of the neutron target is prolonged.

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).

The invention relates to an isotropic thermal neutron radiation field angle distribution uniformity control device and method, and the device is characterized in that a particle accelerator is used for emitting a high-energy charged particle beam with a beam position; the beryllium target is placed along the emission line of the high-energy charged particle beam, and the high-energy charged particle beam bombards the beryllium target to generate charges; the insulation isolation gasket is wound on the outer side of the beryllium target and prevents the charges from being led out from the outside through the beryllium target; and the adjusting assembly is connected with the beryllium target and used for acquiring the electric charge quantity on the beryllium target, and is connected with the particle accelerator and used for adjusting the angle of the high-energy charged particle beam irradiating to the beryllium target. According to the invention, the purposes of preventing the charges from being exported outwards based on the insulation isolation gasket and obtaining the charge quantity by the adjusting assembly to adjust the particle accelerator are achieved, so that after the insulation isolation gasket with low cost is used for isolation, the charge quantity is detected to adjust the particle accelerator, and the technical effect of effectively saving the cost is achieved.

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.

The present invention relates to the technical field of neutron targets and discloses a tantalum and beryllium neutron target system suitable for BNCT. The tantalum and beryllium neutron target system comprises a target plate structure and a target stand for mounting the target plate structure. The target plate structure comprises a tantalum target and a beryllium target, which are bonded into an integrated target plate structure by a high-temperature resistant metal adhesive. The tantalum and beryllium neutron target system suitable for BNCT provided by the present invention solves the problem of low energy utilization and inability to maximize neutron yield in existing designs.

The present invention provides a method, terminal, and medium for obtaining a target thickness of a hydrogen embrittlement-resistant layer of a neutron source target. The method includes: using a physical field fitting method to perform hydrogen diffusivity fitting based on deposition distribution and thermal performance fitting based on energy distribution on a target including a hydrogen embrittlement-resistant layer to obtain a hydrogen atom concentration distribution characteristic and a corresponding temperature distribution characteristic corresponding to the current thickness; detecting whether the hydrogen atom concentration distribution characteristic satisfies a predetermined condition for the hydrogen atom concentration field and whether the temperature distribution characteristic satisfies a predetermined condition for the temperature field; and, if both conditions are satisfied, setting the current thickness of the hydrogen embrittlement-resistant layer as the target thickness of the hydrogen embrittlement-resistant layer. This method makes it possible to quickly and easily obtain a target thickness of the hydrogen embrittlement-resistant layer that is compatible with the physical field performance of other layers in the target, thereby improving the hydrogen resistance performance of the target and effectively improving the overall performance of the target.

The present application relates to the technical field of neutron irradiation, and provides a neutron generating device, comprising a graphite stack, a neutron source, a shielding shell and a plurality of movable plates, wherein the graphite stack forms a radiation cavity and a detection cavity, the neutron source is arranged in the radiation cavity, the neutron beam emitted by the neutron source is moderated by the graphite stack to form thermal neutrons, and a thermal neutron reference radiation field is generated, the shielding shell forms a accommodating space, the graphite stack is arranged in the accommodating space, the shielding shell is provided with a plurality of beam ports connected to the accommodating space, the plurality of movable plates are movably connected to the shielding shell to selectively open or cover the beam ports, wherein the thermal neutron reference radiation field forms an inner calibration area and an outer calibration area, and detector traceability is achieved by placing a detector in the inner calibration area or the outer calibration area.