33 results about "Neutron yield" patented technology

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.

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 application discloses a high-extraction-efficiency ion source structure and sealed neutron tube structure; a TiT thin film target is tightly attached to the inner wall of a closed shell; a target grid is tightly attached to the TiT thin film target, and a negative bias voltage is generated by loading a voltage between the target grid and the closed shell; plasma is generated after a voltage is loaded between a discharge anode and a discharge cathode; the scheme is based on the existing vacuum arc discharge ion source structure and is improved in structure; space is reserved between the discharge cathode and the anode grid for free expansion of the plasma, an open expansion space is provided for the plasma, most of the plasma generated by the discharge can expand into the acceleration zone to obtain energy and bombard the target surface, so that the arc current utilization rate can be increased to about 1%, and the neutron yield can be broken through 1*10 10 n / s.

The invention discloses a neutron beam real-time regulation and control method and system based on two parameters, and the method comprises the steps: collecting the two parameters and a target beam current in real time, and obtaining a data set; an LSTM-Attention initial model is constructed; training, verifying and testing the LSTM-Attention initial model by using the training set, the verification set and the test set to obtain a final neutron beam current control model; the deviation between the target beam current and a set value is monitored in real time, a final neutron beam control model is used for inversion to obtain a two-parameter adjusting quantity, and real-time neutron beam regulation and control are achieved; according to the method, the coupling relation between the two parameters and the beam is considered, the current and the air inflow of the ion source can be adjusted in real time, stable operation of the neutron source beam is ensured, the neutron yield stability is improved, and the application effect in practical application can be improved.

The invention discloses a uranium mine logging instrument based on ultrashort pulse neutrons and a working method thereof, and relates to the field of uranium mine exploration logging. The logging instrument comprises a control communication short section, an ultrashort pulse neutron generator used for emitting fast neutron pulses with the pulse width smaller than 1 microsecond to a stratum, a shielding body and a double-thermal-neutron detection assembly used for detecting thermal neutrons and epithermal neutrons on measuring points consistent in space, all of which are sequentially arranged in the axial direction of the logging instrument. The gamma detector is used for detecting inelastic scattering gamma rays emitted by stratum elements and capturing gamma rays, and the fast neutron detector is used for detecting and outputting source intensity monitoring signals of fast neutron pulses in real time. According to the logging instrument, the ultra-short fast neutron pulse is emitted, the neutron yield is detected in real time, the neutron time spectrum and gamma-ray energy spectrum multi-dimensional information with an accurate timestamp are obtained in a combined mode, high-precision and anti-interference inversion is conducted on the stratum uranium content, and stratum information is obtained efficiently and accurately.

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

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

The invention belongs to the technical field of data processing, and relates to a neutron generator operation state monitoring method and system based on digital twinning. The method comprises the following steps: acquiring real-time operation electrical parameters to construct a virtual twinborn body; inverting the effective deuterium and tritium atom concentration in the target film in real time by using a physical difference equation containing a particle injection item and a thermal diffusion loss item; a beam spot drift correction factor is determined by calculating the difference between the real-time impedance of the neutron tube and the nominal design impedance, the beam spot area of the virtual twin is dynamically corrected, and the problem of prediction model failure caused by electrode ablation is solved; and finally, on the basis of the corrected state parameters, using a multi-parameter product model to predict the neutron yield and perform health degree diagnosis. Transparent monitoring of the internal state of the neutron tube is achieved, the problem of model distortion caused by beam spot drift is effectively solved, and the prediction precision of the whole life cycle is improved.

The invention relates to an accurate stabilization method for the neutron yield of a neutron generator and the neutron generator, and belongs to the technical field of neutron yield control. The accurate stabilization method for the neutron yield of the neutron generator comprises the following steps: executing a first-stage feedback control loop and a second-stage feedback control loop at the same time; the first-stage feedback control ring is configured to control the actual measurement value of the beam to be stabilized to the beam set value by adjusting the microwave power or / and the gas flow according to the deviation between the actual measurement value of the beam and the beam set value; the control period of the first-stage feedback control loop is from millisecond level to second level; the second-stage feedback control loop is configured to determine the variation required by the beam current set value according to the deviation between the actual measurement value of the neutron yield and the neutron yield set value, and update the beam current set value; and the control period of the second-stage feedback control loop is from a second stage to a hundred seconds stage. According to the accurate stabilization method for the neutron yield, long-term accurate and stable control of the neutron yield can be realized, and the response speed is high.

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

The invention discloses a neutron source based on an FRC linear magnetic confinement nuclear fusion device, and relates to the technical field of fusion devices. The neutron source comprises a vacuum chamber for providing a vacuum environment for fusion reaction; the magnet system is arranged outside the vacuum chamber and is used for ionizing gas in the vacuum chamber and generating fusion reaction; the neutron extraction system is arranged in the fusion reaction generation area of the vacuum chamber and is used for extracting epithermal neutrons; the neutron lead-out system comprises a neutron lead-out channel, a shielding and reflecting device and a filter, the shielding and reflecting device is arranged outside the lead-out channel and used for shielding and reflecting neutrons, and the filter is arranged in the neutron lead-out channel and used for filtering fast neutrons, thermal neutrons and photons; the neutron source provided by the invention has the advantages of higher neutron yield, simple and compact structure, effectively reduced overall device volume, low construction and maintenance cost and small nuclear safety prevention and control pressure, and can be used in various fields of medical treatment, scientific research, military industry and the like.

The invention discloses a neutron target with low thermal stress, and relates to the technical field of neutron targets, the neutron target comprises a first target layer and a second target layer, and the non-bombardment surface of the first target layer is attached and welded to one side surface of the second target layer; the first target layer is divided into a central target piece and a plurality of sector ring target pieces distributed around the central target piece by a groove, the depth of the groove extends from the first target layer to the second target layer, the groove bottom of the groove is located on the second target layer, and the material ductility of the second target layer is larger than that of the first target layer. According to the neutron target, the technical problem that the neutron yield is limited due to the thermal stress of the neutron target in the prior art is solved, and the neutron target with low thermal stress and high neutron yield is provided.

The application discloses a kind of uranium mine logging instrument based on ultrashort pulse neutron and working method thereof, it is related to uranium mine exploration well logging field;Logging instrument includes control communication nipple arranged in sequence along its axial direction, ultrashort pulse neutron generator for emitting fast neutron pulse with pulse width less than 1 microsecond to formation, shielding body, dual thermal neutron detection assembly for detecting thermal neutron and superhot neutron on spatially consistent measurement point, gamma detector for detecting non-elastic scattering gamma ray and capture gamma ray emitted by formation element, and fast neutron detector and multichannel synchronization and high-speed acquisition circuit for detecting and outputting source intensity monitoring signal of fast neutron pulse in real time;The logging instrument of the application emits ultrashort fast neutron pulse and detects neutron yield in real time, combines to obtain neutron time spectrum and multi-dimensional information of gamma energy spectrum with accurate time stamp, carries out high-precision, anti-interference inversion to formation uranium content, and efficiently and accurately obtains formation information.

The application discloses a kind of neutron tube structures of accelerating polar adjustable radial extraction penning ion source, including sleeve, the one end inside sleeve is equipped with anode cylinder, the outer embedding of the cylinder body of anode cylinder is equipped with insulator, radial extraction hole is opened in the side of anode and insulator, the outside of radial extraction hole is coaxially equipped with acceleration cylinder with insulator, copper target is equipped at the tail end of acceleration cylinder;When using, adjusting nut, lengthening or compressing corrugated expansion pipe, the distance between acceleration cylinder and discharge cavity is adjusted, then external circuit is added voltage to anode cylinder, under the joint action of electric and magnetic field, gas ionizes, generates ion, ion is extracted through radial extraction hole, at this time, acceleration cylinder applies positive high voltage, ion is accelerated and extracted, and neutron is generated by hitting copper target;The present application is more easily extracted by setting radial extraction hole and configuring corrugated expansion pipe around acceleration cylinder, improves acceleration performance, controls the area of ion beam hitting copper target, improves copper target utilization rate, and improves neutron yield.

The application provides a neutron tube testing device and a testing method. The neutron tube testing device comprises a vacuum mechanism, an atmosphere control mechanism, a feeding mechanism and a supporting mechanism, the vacuum mechanism and the atmosphere control mechanism are both installed on the supporting mechanism, the feeding mechanism is installed in the vacuum mechanism, and the atmosphere control mechanism is connected with the vacuum mechanism. The device is used for testing the service life of a neutron target and the neutron yield of the neutron target, and checking the qualified rate of the neutron target in the production link. The neutron target is tested before the neutron tube is sealed, so that the whole neutron tube is prevented from being scrapped, material waste is avoided, and the research and development testing time is prevented from being delayed. The device is used for researching the influence of different film thicknesses on the neutron yield of the neutron target, the influence of different magnetic field strengths, different extraction hole structures and other factors on the ion source, and the influence of different structure ion sources or different structure accelerating electrodes on the neutron yield, so that the economic cost and time cost of the sealed neutron tube are reduced.

The invention discloses a neutron target system design method and a neutron target system designed by adopting the design method.The neutron target system design method comprises the steps that a solid target and a liquid target are arranged at the same time, and the liquid target is arranged on the side, away from the coming direction of particle beams, of the solid target; obtaining a neutron yield standard value and a neutron yield target value; if the neutron yield standard value is greater than or equal to the neutron yield target value, respectively configuring the thickness of the solid target and the liquid target according to the neutron yield target value; and if the neutron yield standard value is smaller than the neutron yield target value, making a difference between the neutron yield target value and the neutron yield standard value to obtain a neutron yield difference value, and configuring the thickness of the liquid target according to the neutron yield difference value. The technical problems that in the BNCT field, high neutron yield is obtained, particle beam parameters (beam energy and / or beam intensity) correspondingly need to be improved, an accelerator system is complex, the manufacturing cost is high, generated radioactivity is large, and the radioactive waste disposal cost is high are solved.

This invention relates to the field of ion source technology and discloses a transmission system for a small negative high-voltage neutron source. The transmission system includes a transmission tube, a plasma electrode, an extraction electrode, a Helmholtz coil, and an aperture. The transmission tube has a vacuum channel, and the plasma electrode and the extraction electrode are located inside the vacuum channel, downstream of the plasma electrode in the beam transmission direction. The Helmholtz coil is located outside the transmission tube. This transmission system can overcome the technical problem of how to achieve 100 mA beam transmission and beam homogenization within a limited structural size for a small negative high-voltage neutron source. The Helmholtz coil and aperture can effectively suppress the space charge effect of the ion source, enhance the beam transmission efficiency, and improve beam homogenization. Simultaneously, it can reduce the target surface heat load, improve neutron yield, and increase the target's service safety and lifespan.

The application relates to the technical field of neutron generators, in particular to a wireless pyroelectric neutron generator adopting a laser irradiation mode, which comprises a grounding shell, a pyroelectric component, an ion generating component, a magnetic component, a target and a laser emission mechanism with adjustable power; the application can replace the traditional temperature control mode by adopting laser radiation heating, can simultaneously generate a high-voltage electric field and ions for acceleration by laser, can effectively improve neutron yield when ions bombard the target body, can improve the repeatability of neutron yield, can greatly simplify the complexity of the structure, and solves the problems existing in the prior art.

The invention discloses a neutron absolute measurement method of a high-current D-D neutron generator, and belongs to the technical field of neutron generators. The method comprises the following steps: carrying out measurement by adopting latest reaction cross section data of an ENDF-B-VI database and prevention capability data simulated by SRIM-2013; complex integral is converted into summation calculation through thin target approximation, meanwhile, a visual operation program is developed, and the experimental data conversion process is simplified; according to the method, D-D neutron yield measurement is realized by adopting an accompanying proton measurement method; in the measurement process, two reaction channels exist in D-D fusion under a low-energy deuterium beam, and protons with energy of 3.05 MeV are preferentially selected as accompanying particles. According to the method, the uncertainty of correction factors can be reduced, the problem of thick target calculation is solved, the operation is simplified, and accurate measurement of the neutron yield and flux of the high-current D-D neutron generator and rapid conversion from experimental data to a target result are realized.

The application discloses a convex target neutron tube, which comprises a magnetic steel ring, a target sheet, a target body, a shell and an accelerating electrode, the accelerating electrode is fixedly connected with the target body, the magnetic steel ring is arranged on the outer side of the accelerating electrode, and the magnetic steel ring is close to the end surface of the target body connected with the accelerating electrode; the target sheet is arranged in the interior of the target body and is fixedly connected with the target body; the shell is arranged on the outer side of the accelerating electrode, one end of the shell is connected with the target body, and the other end is connected with a source structure member; the magnetic steel ring is arranged on the outer side of the accelerating electrode, the magnetic steel ring further forms an axial dispersion magnetic field on the outer convex spherical surface of the target sheet, a secondary electron magnetic suppression structure of the neutron tube is formed, and the secondary electron can be effectively suppressed; the problem that the secondary electron is accelerated by the accelerating electric field to form a harmful target flow, the power consumption of the neutron tube is increased, and the working life index is affected is solved; the outer convex spherical target surface is a gradient distribution deuterium absorption titanium film, the utilization rate of the deuterium in the target of the neutron tube is improved, and the neutron yield index of the neutron tube is improved.

The application relates to the technical field of composite targets, and discloses a composite breeding target system for BNCT, which comprises a Be-Li composite target and a primary breeding system, the primary breeding system is located at the back of the Be-Li composite target, and the two form a composite target structure, wherein the primary breeding system comprises a uranium layer and an aluminum substrate layer, the uranium layer is attached to the aluminum substrate layer, the output efficiency and quality of neutrons can be effectively improved through optimization of a neutron generation and breeding process, thereby providing a more efficient neutron source for BNCT, the composite breeding target system for BNCT can improve the neutron yield after proton targeting, and can also make the neutron energy generated by the Li layer consistent with the neutron energy generated by the Be layer.

According to the Am-Li neutron source preparation method based on molecular assembly, metal-organic framework (MOFs) molecular assembly serves as a core, Am < 3 + > and Li < + > are accurately connected through coordinate bonds to achieve field assembly of a neutron source, controllable release is achieved, the raw material utilization rate and the neutron yield are high, and the method is suitable for large-scale production. The used raw materials Am (NO), LiCOs, ligands and the like are all in a non-radioactive source state, can be transported independently, do not need lead shielding, are low in transportation cost, do not need to be reported in advance, and are adaptive to portable scenes such as the field and the site.

This invention belongs to the field of neutron tube control technology, specifically relating to a method and system for controlling tritium charging in a self-targeting neutron tube. The method includes: real-time acquisition of the ion source current and accelerating electrode voltage of the self-targeting neutron tube; obtaining smoothed real-time operating parameters using a weighted moving average filtering algorithm; matching a hydrogen storage tank heating voltage reference value according to a preset target neutron yield; and calculating the dynamic compensation amount of the heating voltage using a fuzzy PID algorithm based on the deviation and rate of change between the real-time ion source current and the target current; and superimposing the reference value and the dynamic compensation amount to obtain a PID control voltage, driving the hydrogen storage tank to adjust the tritium release rate. This invention, through filtering and dynamic compensation control, solves the problem of unstable tritium charging caused by large fluctuations in the ion source current and thermal inertia hysteresis, thereby improving the stability of the neutron yield and the service life of the neutron tube.

The present application belongs to the technical field of data processing, and relates to a neutron generator running state monitoring method and system based on digital twinning. The method collects real-time running electric parameters to construct a virtual twin; a physical difference equation containing a particle injection term and a thermal diffusion loss term is used to real-time inverse the effective deuterium-tritium atom concentration in the target film; the difference between the real-time impedance of the neutron tube and the nominal design impedance is calculated to determine the beam spot drift correction factor, and the beam spot area of the virtual twin is dynamically corrected to solve the problem of prediction model failure caused by electrode ablation; finally, based on the corrected state parameters, a multi-parameter product model is used to predict the neutron yield and perform health degree diagnosis. The present application realizes the transparent monitoring of the internal state of the neutron tube, effectively solves the model distortion problem caused by beam spot drift, and improves the prediction accuracy throughout the life cycle.

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

The application relates to a magnetic confinement fusion plasma temperature diagnosis method, device and equipment, wherein the method comprises the following steps: establishing a neutron yield database, including a thermonuclear fusion neutron yield database and a beam-target reaction neutron yield database; collecting ion density and total neutron yield of external experimental equipment; assuming that only beam-target reaction exists in an initial stage, obtaining an initial temperature estimation value based on the ion density and the total neutron yield; obtaining first neutron yield and second neutron yield based on the initial temperature estimation value and the ion density, and obtaining theoretical total neutron yield; comparing the difference between the total neutron yield and the theoretical total neutron yield until convergence, obtaining the temperature estimation value as the plasma temperature; and outputting a diagnosis result as an initial temperature of the next moment to realize time sequence evolution analysis. The scheme fully utilizes the thermonuclear fusion and beam-target reaction database, effectively distinguishes the contributions of the two types of reactions to the neutron yield, and avoids the limitations of a traditional single reaction model.

The invention relates to the technical field of compact accelerator neutron sources, in particular to a device for actively absorbing secondary electrons. In order to solve the problems that a compact neutron source based on the electron cyclotron resonance technology can generate a large number of secondary electrons in the beam-target action process, and disordered escape of the electrons easily causes main beam interference, neutron yield reduction and system stability damage, the invention provides the following technical scheme: the compact neutron source comprises a neutron target, the neutron target is in threaded connection with an extraction electrode; the secondary electron absorption structure and the supporting screw are located between the neutron target and the extraction electrode, the secondary electron absorption structure is fixed over the neutron target through the supporting screw, and the extraction electrode is connected with the neutron target in a matched mode. According to the invention, the focusing and bombardment efficiency of the main beam is guaranteed, the neutron yield is improved, the plasma is kept pure and stable, the ECR neutron source is assisted to develop towards high-efficiency and long-life industrial equipment, and the requirements of mobile detection and embedded application are met.

The present application relates to solid-state lithium target water cooling technical field, especially to a kind of water-cooling support device for boron neutron capture therapy solid-state lithium target.Its technical scheme includes providing support water-cooled base, the top of water-cooled base is equipped with angle of inclination support bracket, the cross section of angle of inclination support bracket is right triangle structure setting, the hypotenuse of angle of inclination support bracket is equipped with structural material, cooling assembly is arranged on the structural material;The side of structural material away from angle of inclination support bracket is fixedly installed with heat sink material, one side of heat sink material is uniformly provided with cooling channel rib strip.The whole structure of the present application is compact, can simply, conveniently and efficiently solve the heat removal problem of accelerator neutron source BNCT solid-state lithium target, guarantee the continuous safe and stable operation of neutron source system, meet the demand of high-flux neutron yield, effectively solve the short life of lithium film evaporation, melting and other problems and the unstable problem of target structure due to heat.

The application relates to a neutron source with an ion beam guiding function, which comprises an ion source, an accelerating electrode, a neutron target group and an insulated flow guide mechanism, the ion source is used for ionizing gas to generate an ion beam; the neutron target group is installed on one side of the ion source, the accelerating electrode is installed between the ion source and the neutron target group, and the flow guide mechanism is installed between the ion source and the neutron target group; the accelerating electrode is used for applying a voltage and forming an electric field one between the accelerating electrode and the ion source, the electric field one accelerates the ion beam, and charged ions in the ion beam deposit on the inner surface of the flow guide mechanism until a stable electric field two is formed, the electric field two focuses and guides the ion beam entering the inside of the flow guide mechanism, and the ion beam bombards the neutron target group to generate neutrons. The application has the advantages of simple structure, reasonable design, realization of ion beam focusing and collimation, improvement of the neutron yield of the neutron generator, adjustment of the positions of the neutron target and the flow guide mechanism, generation of neutron beams with different outgoing directions and multiple functions.