574results 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.

A neutron capture therapy system includes a neutron generating device and a beam shaping assembly. The neutron capture therapy system further includes a concrete wall accommodating the neutron generating device and the beam shaping assembly and shielding radiations generated by the neutron generating device and the beam shaping assembly, the concrete wall and a reinforcing portion at least partially disposed in the concrete wall are provided to support the beam shaping assembly, and more than 90% of weight of a material of the reinforcing portion is composed of at least one element of C, H, O, N, Si, Al, Mg, Li, B, Mn, Cu, Zn, S, Ca, and Ti. In the neutron capture therapy system, the reinforcing portion disposed in the concrete wall has good anti-activation performance. Therefore, compared with a conventional reinforced concrete structure, the radiation is further attenuated.

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.

A neutron generator with an ion source within a housing may be used for generating neutrons for neutron logging downhole in a wellbore. The ion source within the housing of the neutron generator may include a hot cathode, an ion source cylinder, a first grid separated from the ion source cylinder, and an extractor separated from the ion source cylinder, the extractor having a second grid.

The double-sided cooling capsule target chamber comprises a capsule target piece assembly, a bearing assembly, a target chamber head assembly and a target chamber tail assembly, and the capsule target piece assembly is circular; a groove part and a channel communicated with the groove part are formed in the bearing assembly, and a capsule target piece assembly is arranged in the groove part; a helium cooling channel and a water cooling channel are respectively arranged in the bearing component corresponding to the front surface and the back surface of the capsule target sheet component; the target chamber head assembly is fixed at one end of the bearing assembly, and the target chamber head assembly is provided with a leading-in part for leading an accelerator particle beam into the channel; the target chamber tail assembly is fixed to the other end of the bearing assembly. The double-face cooling effect of copper supporting face water cooling and aluminum supporting face gas cooling can be achieved on the capsule target piece assembly, and the use feasibility of target pieces made of different heat conduction performance materials is improved; the irradiation efficiency is improved, the manufacturing cost is reduced, and conveying and cooling are facilitated; and meanwhile, the treatment capacity of dissolution and separation of the irradiated target sheet can be reduced, and the post-treatment cost is reduced.

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.

Embodiments of systems, devices, and methods relate to initiating beam transport for an accelerator system. An example method includes increasing a bias voltage of one or more electrodes of the accelerator system to a first voltage level and extracting a charged particle beam from a beam source such that the beam is transported through the accelerator system. The beam has a beam current at a first beam current level that results in a first transient voltage drop of the accelerator system within a threshold. The method further includes increasing the beam current at a rate that results in one or more subsequent transient voltage drops of the accelerator system until the accelerator system has reached nominal conditions. The one or more subsequent transient voltage drops are within the threshold. Another example method includes biasing one or more electrodes of an accelerator system to a voltage level and selectively extracting, according to a duty cycle function, a charged particle beam from a beam source such that the charged particle beam is transported through the accelerator system. The duty cycle function can be linear or non-linear and can include a frequency f. The duty cycle function can include a variable pulse duration such that the variable pulse duration increases over time with each selective extraction of the charged particle beam.

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 invention discloses a compact magnetic deflection system for neutral beam injection. The compact magnetic deflection system comprises an iron yoke assembly, two magnet assemblies with the same structure and a magnet protection assembly, the iron yoke assembly is of a rectangular frame structure and forms a complete magnetic loop, the two magnet assemblies are oppositely arranged in the iron yoke assembly, and a channel is reserved between the two magnet assemblies. The magnet protection assembly surrounds the two magnet assemblies; the magnet assembly comprises a magnet exciting coil box, an iron core and an electrified coil, two space grooves are formed in the excitation coil box in a rectangular-ambulatory-plane mode, the iron core is located in the space groove in the inner layer, the electrified coil is located in the space groove in the outer layer, and the head end and the tail end of the electrified coil extend out of the side edge of the excitation coil box in the same direction; charged ions flexibly deflect out of an original beam line channel by changing the current of the electrified coil or the number of turns of the coil. According to the invention, mixed charged ion beams can be effectively filtered out, and purified neutral beam injection is realized.

The invention relates to the design of a radium target for preparing 225Ac through a photo-nuclear reaction in the technical field of production of a mechanical produced medical isotope 225Ac, in particular to a 226Ra isotope target for producing 225Ac and application of the 226Ra isotope target. The 226Ra isotope target comprises a nickel substrate, a 226Ra isotope sample, a nickel electroplated layer and a nickel protective shell; wherein the 226Ra isotope samples are uniformly concentrated at the central position of the nickel substrate, the nickel electroplated layer covers the outer surfaces of the 226Ra isotope samples, and the nickel substrate and the nickel electroplated layer wrap the 226Ra isotope samples in the middle; and the nickel protective shell wraps the nickel electroplated layer. The 226Ra isotope target can be applied to an electron linear accelerator and can be used as a raw material target for producing 225Ac through a photo-nuclear reaction, and the production quantity of the 225Ac isotope can be increased.

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 provides a neutron generator, an element detection method, electronic equipment and a storage medium, the neutron generator comprises a target material, the target material is provided with a neutron generation cavity, a particle flow inlet and a neutron outlet, and the particle flow inlet and the neutron outlet are both communicated with the neutron generation cavity; wherein the target material is configured to controllably move to adjust the orientation of the neutron outlet, and the target material is configured to enable the directions of at least two photons emitted from the neutron outlet to be different after being bombarded by the particle flow. The problem of direction information loss caused by an existing flat plate type target material can be solved, the detection accuracy is improved, detection of all positions of the to-be-detected object can be completed at a time after the target material is combined with a detector for use, and the detection workload is reduced.

Passivation regions and device configurations are described herein. The passivation regions can be configured to seal against diffusion of an objective material from an underlying region into and / or through the passivation region. The passivation regions can also be configured to seal against diffusion of an externally sourced or ambient substance into and / or through the passivation region towards the underlying region.

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 invention relates to the technical field of isotope production equipment, in particular to a target device for isotope production, which comprises a target chamber and a target assembly, the target chamber is provided with an inner cavity, and a plurality of beam holes arranged in an array are formed in the face, facing beam current, of the target chamber. The beam holes are covered with target windows. The target assembly is inserted into the target chamber and comprises a target frame and a target capsule; the target frames and the target windows are arranged in a one-to-one correspondence manner, and at least one mounting position for mounting the target capsule is arranged in each target frame in the axial direction of the beam hole; openings are formed in the two sides of each target frame, the side openings of the multiple target frames correspond to one another and define an independent cooling liquid flow channel with the inner wall of the target chamber, and gaps are formed in the two sides, in the axial direction of the beam hole, of each target capsule and used for allowing cooling liquid to flow through. A detachable cover plate assembly is arranged at the top of the target chamber, and the target assembly is integrally sealed in the target chamber in an assembling state. The scheme is used for solving the defects that the target assembly is inconvenient to disassemble and assemble, the safety is low and the cooling water sealing is difficult to guarantee in a high-radiation dose environment.

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 relates to the technical field of neutron sources and discloses a rotating neutron target heat dissipation method, a rotating neutron target and a neutron target system.The rotating neutron target heat dissipation method is characterized in that a heat exchange structure is arranged on the side face of a target piece, and a cooling medium is introduced into the heat exchange structure and used for assisting in heat dissipation of the target piece; according to the invention, the technical problem that in the prior art, a beam bombardment area coincides with the cooling water flow channel of the neutron target, the heat dissipation effect of the target sheet can be achieved, neutrons generated by the neutron target in the beam direction are slowed down, and the quality of the neutron beam is reduced can be solved; according to the invention, on the premise of maintaining effective heat dissipation and cooling of the neutron target, a flow bombardment area can be prevented from being overlapped with the cooling water flow channel of the neutron target, so that high-quality neutron beams can be output at the same time.

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 target for a neutron generation device includes a target material that is to be irradiated with a proton beam to generate neutrons; a substrate in which a recessed portion that holds the target material is provided; and a metal foil for sealing the target material held in the recessed portion. The target material is a lithium alloy material in which a part or an entire portion of lithium is alloyed. The target material and the substrate are alloyed and joined together. A method for producing a target involves placing a precursor made of metal lithium or a lithium alloy in the recessed portion; alloying the precursor and the substrate with each other to be joined together by heating the substrate and the precursor to melt the precursor, and then, solidifying the precursor; and joining the metal foil on the substrate to which the precursor has been joined.

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.