121 results about "Proton" patented technology

A superconducting proton cyclotron (100). The superconducting proton cyclotron (100) comprises a main cyclotron system (10), a cyclotron auxiliary system (20) and a cyclotron control system (30). The main cyclotron system (10) comprises an ion source (11), a central region (12), a superconducting magnet system (13), a radio frequency system (14) and a lead-out region (15). The ion source (11) is used for generating a proton beam; the central region (12) is used for leading out the proton beam of the ion source (11) and performing beam focusing inside the central region (12); the radio frequency system (14) leads out and accelerates the beam of the central region (12); a static magnetic field generated by the superconducting magnet system (13) can constrain the proton beam and accelerate same to target energy; the lead-out region (15) can lead out the proton beam.

The invention discloses a compact high-energy gamma generator for special nuclear material checking and a checking method.The gamma generator comprises a shell and an ion source, the shell is internally provided with a high-pressure vacuum cavity, the ion source is arranged at the left end of the high-pressure vacuum cavity, the right end of the high-pressure vacuum cavity is provided with a high-pressure connector system, and the left end of the high-pressure connector system is connected with a leading-out accelerating electrode; a target holder is arranged in the extraction accelerating electrode, and a boron target sheet is mounted on the target holder; negative high voltage is fed into the extraction accelerating electrode through the high-voltage connector system, an electric field is formed between the extraction accelerating electrode and the anode of the ion source, the proton beam is extracted and accelerated by the electric field and then bombarded on the boron target sheet, 11B (p, gamma) 12C resonance radiation capture reaction is carried out, and high-energy gamma rays are released; the gamma ray and the special nuclear material are subjected to a photofission reaction to emit instant neutrons and delayed neutrons, and the detection of the special nuclear material is realized by measuring the instant neutrons and the delayed neutrons. The device is compact in structure, high in detection sensitivity, short in detection time, low in interference and long in service life, and has very high application value.

The present invention relates to a cyclotron comprising first and second internal ion sources configured to form first and second beams of identical charged particles wherein the cyclotron is further configured to generate a local asymmetry of an accelerating electric and / or magnetic field, the first beam and the second beam are combined to form a combined beam and the combined beam passes through a single extraction outlet. The invention also relates to an acceleration system comprising N cyclotrons, where M cyclotrons are the cyclotrons according to the invention, Mgt; 0. The invention also relates to a device for treating a patient by BNCT, comprising: an acceleration system according to the invention; a target configured to emit an epithermal neutron beam when bombarded with the proton or deuteron multi-combination beam; and a treatment region configured to hold a patient to be treated within the treatment region.

To solve the problem that muon is supplemented to a generated substance after nuclear fusion, not to a nuclear fusion fuel substance, and muon catalyzed fusion reaction is unlikely to proceed because in a well-known muon-catalyzed fusion, muon is adhered to / captured / trapped by helium to be a generated substance after nuclear fusion, not to a fusion fuel substance such as hydrogen / heavy hydrogen D / tritium T, and catalyzed fusion reaction stops; and to propose a system which is unlikely to generate a neutron.SOLUTION: When nuclear fusion of an atomic nucleus occurs in muon catalyzed fusion, electric charges of atomic nucleus of a substance generated by nuclear fusion is used for a nuclear fusion reaction system which has a feature smaller than electric charges of an atomic nucleus of an atom to become nuclear fusion fuel. To be specific, a muon catalyzed fusion system using borohydride (diborane or the like) including proton as well as boron for nuclear fusion fuel is proposed.SELECTED DRAWING: Figure 8

The utility model provides a kind of proton acceleration system, neutron generating device and isotope generating device.The proton acceleration system includes radio frequency quadrupole acceleration module, at least has radio frequency quadrupole accelerator;Drift tube linear accelerator module, at least has drift tube linear accelerator.Based on the above-mentioned proton acceleration system, first by radio frequency quadrupole acceleration module to proton beam is accelerated to handle, so that the energy of proton beam reaches first energy value;Further energy adjustment processing is carried out to the proton beam of first energy value by drift tube linear accelerator module, so that the energy of proton beam reaches the second energy value that meets requirements.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

The application discloses a rapid detection method of paraffin in beeswax. The detection method comprises the following steps: dissolving the to-be-detected beeswax sample by using a deuterium solvent to perform nuclear magnetic resonance hydrogen spectrum test, and qualitatively and quantitatively analyzing the paraffin in the beeswax according to the nuclear magnetic resonance hydrogen spectrum result. Two conditions need to be met simultaneously when using the nuclear magnetic hydrogen spectrum to judge whether the paraffin is doped in the beeswax: (1) an ester characteristic proton peak appears near the chemical shift of 4.07 ppm; and (2) the relative integral intensity of the alkyl proton peak in the chemical shift range of 0.9-1.58 ppm is obviously enhanced compared with a standard spectrum. The detection method is simple and rapid, has good linear relationship, high accuracy and good repeatability.

A process for producing technetium-99m from a molybdenum-100 metal powder, comprising the steps of:(i) irradiating in a substantially oxygen-free environment, a hardened sintered target plate coated with a Mo-100 metal, with protons produced by a cyclotron;(ii) dissolving molybdenum ions and technetium ions from the irradiated target plate with an H2O2 solution to form an oxide solution;(iv) raising the pH of the oxide solution to about 14;(v) flowing the pH-adjusted oxide solution through a resin column to immobilize K[TcO4] ions thereon and to elute K2[MoO4] ions therefrom;(vi) eluting the bound K[TcO4] ions from the resin column;(vii) flowing the eluted K[TcO4] ions through an alumina column to immobilize K[TcO4] ions thereon;(viii) washing the immobilized K[TcO4] ions with water;(ix) eluting the immobilized K[TcO4] ions with a saline solution; and(x) recovering the eluted Na[TcO4] ions.

The invention discloses a rapid analysis method for single event upset of an SRAM (Static Random Access Memory) caused by MeV energy region protons, which comprises the following steps: establishing a target geometric model according to a device structure of the SRAM; constructing a material parameter database; iteratively simulating the transportation process of protons in the target material geometric model and acquiring the total energy deposition of the protons in the sensitive volume based on a material parameter database by adopting a mixed algorithm combining a continuous energy loss model and a discrete scattering model; the total energy deposition of each proton in the sensitive volume is compared with a preset energy deposition threshold value, if the total energy deposition exceeds the threshold value, it is judged that a single event upset event occurs, and the total number of events is counted; and based on the total number of events, the total number of incident protons, the total number of bits of the SRAM and the surface area of the target geometric model, obtaining the single event upset cross section.

The application provides an integrated scanning magnet and a proton heavy ion treatment device, which can be applied to the technical field of particle accelerators. The integrated scanning magnet comprises a core, a first scanning coil, a second scanning coil group, a three-dimensional adjustable base and a water distributor. The first scanning coil is symmetrically arranged along a first horizontal direction perpendicular to the propagation direction of the beam, and is used for generating a first deflection magnetic field along the first horizontal direction. The second scanning coil group is symmetrically arranged along a second horizontal direction perpendicular to the propagation direction of the beam, and is used for generating a second deflection magnetic field along the second horizontal direction. The second scanning coil group comprises a first group of coils and a second group of coils, and the second group of coils is used for optimizing the excitation efficiency of the window frame core. The core adopts a window frame structure, and the end plate and the core body are communicated with a slot to reduce the eddy current loss. The X and Y direction scanning coils are integrated in the same core, the Z direction size of the treatment head is significantly shortened, and the weight of the rotating gantry is reduced.

The present invention discloses a dose calibration system and method for a wide-energy-spectrum neutron radiation detector. The system comprises a neutron target device, a deflection system, a beam waste bin, a neutron collimator, and a test bench, which are sequentially arranged. The neutron target device is used to generate high-yield neutrons; the deflection system is used to deflect the proton beam remaining after passing through the neutron target device; the beam waste bin is used to collect and shield the deflected proton beam and radiation field; the neutron collimator is used to shield the background neutron radiation field that needs to be eliminated; and the test bench is used to calibrate the high-energy, narrow-spectrum neutron dose after the background neutron radiation field is eliminated. This solution can improve the accuracy of high-energy neutron dose calibration for a wide-energy-spectrum neutron radiation detector.

The invention relates to a proton flow reactor for use in storing and releasing energy. In use, a slurry of storage particles in a liquid electrolyte may pass through a first half cell of the proton flow reactor. When the proton flow reactor is in charge mode, protons are bonded or otherwise attracted to the storage particles to form charged storage particles charged with hydrogen, which can hen be stored and / or transported for later use. When the proton flow reactor is in discharge mode, protons are removed from the charged storage particles to fuel an electrochemical reaction, thereby generating electricity. Alternatively, the proton flow reactor in discharge mode can be configured to generate hydrogen gas directly from the in-flowing charged carbon particles.

A nuclear fusion device and a method for controlling nuclear fusion intensity are disclosed. The nuclear fusion device includes a nuclear beam generation unit that emits a nuclear beam, a reaction vessel filled with nuclear fusion material, a thermal energy output system and an electrical energy output system that convert the energy produced by the nuclear fusion reaction into thermal energy and electrical energy for output. The reaction vessel receives the nuclear beam, which reacts with the nuclear fusion material inside to produce neutrons, achieving a neutron nuclear fusion cycle reaction and releasing energy. The nuclear beam includes at least one of a triton beam with a single nucleus energy of 50 KeV-1 MeV, a deuteron beam with a single nucleus energy of 100 KeV-5 MeV, and a proton beam with a single nucleus energy of 2-10 MeV; the nuclear fusion material includes polyatomic molecules, which at least include 6LiD and 7LiD.

The invention provides a simulation method and system for analyzing material multi-scale evolution under proton and electron comprehensive irradiation, and belongs to the field of material irradiation effect simulation and performance evaluation. The problems that an existing entity irradiation experiment is high in cost, single in simulation method, incapable of equivalently integrating an irradiation environment and lack of defects-insufficient performance association are solved. The method comprises the following steps: calculating and screening PKA atom information of proton and electron irradiation; constructing a PKA spectrum corresponding to protons / electrons under a continuous energy spectrum; the PKA irradiation process is coupled with other atomic scale processes and is used for an equivalent comprehensive irradiation experiment; carrying out high-throughput PKA molecular dynamics calculation and material defect analysis; defect-performance correlation analysis and comprehensive irradiation performance evaluation are carried out. According to the method, the limitation of entity experiments is broken through, the research cost is greatly reduced, the research period is shortened, and irradiation parameters can be flexibly regulated and controlled; the multi-scale process accurate coupling can be realized, and the problem that the comprehensive irradiation effect cannot be reflected by single simulation is solved.

The application relates to a synchrotron for a proton-helium ion therapy device, which comprises eight dipole deflection magnets connected in sequence through eight straight-line sections to form a ring structure, the deflection angle of the eight dipole deflection magnets is 45 degrees, and the maximum magnetic field strength is 2.4T; the eight straight-line sections comprise four long straight-line sections and four short straight-line sections, which are used for accelerating the helium ion beam from an injection energy of 8-10 MeV / u to 200-235 MeV / u and leading out for helium ion therapy, or accelerating the proton beam from an injection energy of 8-10 MeV to 200-750 MeV and leading out for proton therapy. According to the synchrotron for the proton-helium ion therapy device, the structure is very compact, unnecessary gaps and magnet elements are reduced, the circumference of the whole accelerator is reduced, the space of the synchrotron is effectively utilized, and the construction cost of the device and the building is reduced to the maximum extent, and the treatment cost is reduced.

To provide an estimation device, an estimation method, and a program capable of estimating an SEU cross section with high accuracy.SOLUTION: A measurement unit 12 counts the number of SEUs generated when a semiconductor device 13 is irradiated with neutrons or protons emitted from a radiation source 11 to measure an SEU probability, a setting unit 21 sets an arithmetic expression for calculating the SEU probability based on a model function simulating an SEU cross section, a calculation unit 22 calculates an estimated value of the SEU probability based on the arithmetic expression, and a comparison unit 23 compares a measured value of the SEU probability with the estimated value and changes a model parameter included in the model function such that the measured value matches the estimated value. The setting unit 21 changes the model function using the model parameter changed by the comparison unit 23, corrects the model function based on the SEU probability measured by the measurement unit 12 when the radiation source 11 irradiates the semiconductor device 13 with protons, and estimates the corrected model function as the SEU cross section.SELECTED DRAWING: Figure 1

The invention relates to a design method of a four-proton beam ADS device, and the method comprises the steps: building a reactor model which comprises a shielding layer, a reflecting layer, a fuel region and a heavy metal target; the heavy metal target comprises a central heavy metal target and three surrounding heavy metal targets; two accelerators are arranged for the heavy metal target and are respectively a first accelerator used for bombarding the central heavy metal target and a second accelerator used for bombarding the three surrounding heavy metal targets in turn so as to generate a four-proton beam; establishing an exogenous disturbance point reactor neutron kinetic equation; obtaining dynamic parameters in the reactor model based on the reactor model and the accelerator; determining a power upper limit of the reactor model based on the temperature limit value of each structure in the reactor model; the temperature limit value of each structure is based on the temperature corresponding to the melting point of the material of each structure; and if the reactor power exceeds the power upper limit, adjusting the structure parameters of the reactor model and the operation parameters of the accelerator.

A system for nuclear power generation can include an accelerator-driven subcritical nuclear reactor that operates using molten-salt fuel. The reactor includes a target positioned to receive a proton beam and to be cooled by the molten-salt fuel. A voltage signal is applied to an electrode in contact with the molten-salt fuel in the reactor for controlling corrosion of the target and other portions of the reactor. In one embodiment, the target is used as the electrode. In another embodiment, an electrode other than the target is used.

The present invention relates to a composite shielding method for total radiation dose in medium-orbit space, comprising the following steps: S1. calculating the total radiation dose at any position of a spacecraft in medium-orbit space; S2. calculating the energy loss per unit distance of protons in the material; S3. selecting a shielding material based on the energy loss per unit distance of protons in the material; and S4. coating aluminum with the selected shielding material to construct a composite shielding material for spacecraft radiation protection in medium-orbit space. The method provides reliable protection for spacecraft against the total radiation dose in medium-orbit space at a minimal cost in mass and volume.

The application discloses a kind of proton, negative hydrogen ion, hydrogen atom three charge state beam extraction device, its characteristics are: in the trajectory of beam acceleration to extraction energy, there is proton, negative hydrogen ion, hydrogen atom three charge state beam extraction device;The three charge state or double-charge state beam extraction device is equipped with stripping target and / or electrostatic deflection plate combined by different thickness and different position stripping film, the different position stripping film is used to adjust the proportion of each component beam online, the different thickness refers to according to the demand of multi-charge state beam extraction, stripping film is set to different thickness;The different position refers to on the trajectory of beam extraction, the front and back position of the multiple stripping films is different and the radial position is different between each other.The application solves the problem that the prior art can only extract single-charge state beam, and can only adjust the total flow intensity of each charge state beam online, but cannot adjust the flow intensity of each charge state beam respectively.

To provide a method for analyzing the higher-order structure of a nucleic acid.SOLUTION: Detecting a peak of imino proton within a range of chemical shift values of 10.0 to 16. 0ppm in a proton nuclear magnetic resonance spectrum; Determining the types of base pairs, optionally performing principal component and clustering analyses of the circular dichroism spectra, and optionally performing circular dichroism temperature shift measurements at single wavelengths in the range of 220 to 320nm; A step of performing curve fitting using a thermodynamic equilibrium model and performing evaluation, a step of performing ultraviolet temperature change measurement at a single wave length within a range of 290 to 300nm in some cases, and a step of determining that two or more types of nucleic acid higher-order structures including a guanine quadruplex structure are formed in a case where fitting to a state model indicating equilibrium of two or more states is shown, A step of determining that a guanine quadruplex structure is not formed when no fit to any state model indicating an equilibrium of two or more states is shown.SELECTED DRAWING: None

The invention discloses a solid-state target system for producing multiple nuclides by multiple particles, and relates to the technical field of radionuclides. The target cavity is arranged on the right side of the accelerator; a combined target is arranged in the target cavity, and various radionuclides are generated after the combined target is irradiated by the accelerator; the fixing device is arranged in the target cavity, connected with the combined target and used for fixing the combined target; and the cooling system is connected with the target cavity and is used for cooling the combined target. The invention solves the problem of single type of nuclides produced by an accelerator in the prior art, and provides a solid-state target system for producing multiple nuclides by multiple particles.

Disclosed herein are methods for producing a radium or barium target. The methods include providing an organic-aqueous electrolyte bath solution comprising radium or barium ions, exposing a deposition surface of a target substrate to the electrolyte bath solution, wherein the target substrate comprises at least one of copper and aluminum, and wherein the deposition surface comprises at least one of copper, aluminum, gold, platinum, rhodium or silver, and applying an electric potential between an anode and the target substrate for a deposition cycle time, thereby electrodepositing a layer of radium or barium containing material out of the bath solution and onto the deposition surface. Also disclosed are targets for subsequent exposure to an accelerated proton beam.

The application discloses a multi-charge-state beam extraction device for a negative hydrogen ion cyclotron, which comprises the following steps: arranging a three-charge-state beam extraction device of protons, negative hydrogen ions and hydrogen atoms on the track of the accelerated beam to an extraction energy; or arranging a double-charge-state beam extraction device of protons and negative hydrogen ions; or arranging a double-charge-state beam extraction device of protons and hydrogen atoms; and the three-charge-state or double-charge-state beam extraction device is provided with a stripping target and / or an electrostatic deflection plate which are combined by stripping films with different thicknesses and different positions, the different position stripping films are used for online adjusting the proportion of each component beam, and the different positions refer to the front and rear positions and the radial positions of the plurality of stripping films on the track of the beam extraction. The application solves the problem that the prior art can only extract a single-charge-state beam and can only online adjust the total flow intensity of each charge-state beam but cannot adjust the flow intensity of each charge-state beam.

The invention discloses a method for preparing 67Ga, 67Cu and 64Cu through irradiation of a medium-high energy accelerator, the method is based on a composite target composed of a first target material 70Zn and a second target material 68Zn, and the method comprises the following steps: step 1, when protons react with the first target material 70Zn, the half-life period of impurity nuclide 66Ga is smaller than that of 67Ga, and the half-life period of 64Cu is smaller than that of 67Cu; therefore, the division of the medium-high energy region is based on the standard of ensuring the maximum yield of 67Ga and 67Cu; and 2, when protons penetrate through the first target material and the second target material 68Zn to react, because the half-life period of impurity nuclide 67Cu is greater than that of 64Cu, the division of a low-energy region, the irradiation time and the number of cooling days meet the standard that the proportion of 64Cu / (64Cu + 67Cu) is greater than 99%. According to the method, production of several nuclides is considered, the energy interval suitable for production of each nuclide is determined through Monte Carlo simulation and theoretical calculation methods in one-time production, production of multiple nuclides is considered at the same time, and the purity of the target nuclide is larger than 99%.

The invention relates to the technical field of magnesium alloys, and discloses a high-strength, high-thermal-conductivity and high-radiation-shielding magnesium alloy and a preparation method thereof, and the magnesium alloy comprises the following chemical components in percentage by mass: 0.1-9.0 wt% of Gd, 3.0-10.0 wt% of Zn, 0.1-0.8 wt% of Zr, 0.1-0.8 wt% of Mn, and the balance of Mg and inevitable impurity elements. According to the invention, a given proton / electron / neutron protection index of a spacecraft key component is satisfied, and the lightweight advantage is obvious.

The present invention discloses a method for obtaining the energy spectrum and angular distribution of a deuterium-tritium neutron source. The method adopts a D-T neutron radiation field measurement system based on a SiC detector, can simultaneously measure the companion particles of the two reactions, can distinguish them in the energy spectrum, and obtain the counting rates of alpha particles and protons; takes into account the influence of the D-D reaction caused by target deposition in the D-T reaction, obtains the energy spectrum and angular distribution of the D-T and D-D neutron sources, and effectively improves the accuracy of the energy spectrum and angular distribution; the method of the present invention has no requirements for target tube-related parameters such as a pipeline and a grating for the companion particles, is simple to operate, only needs to measure a set of data to obtain the energy spectrum distribution in the entire space, does not need to measure different angles one by one, and can measure all D-T neutron sources; and the method of the present invention can be applied to a DC beam or pulsed beam D-T accelerator neutron source with a reserved companion particle channel, especially when there is deuterium beam deposition on the target, and can more accurately obtain the energy spectrum and angular distribution of the D-T neutron source.

The present invention discloses a device and method for inverting lunar rock types through annihilation radiation, belonging to the technical field of lunar geological structure detection. The method uses a proton accelerator to obtain high-current proton bombardment of typical lunar rock composition samples, and simultaneously uses a detector to measure the induced gamma energy spectrum information generated by the samples. The proton stream bombards the samples to be tested, obtains the annihilation radiation count rate in the 511keV energy window and the count rate in the 969-1133keV characteristic peak area of ​​different samples to be tested, and calculates the ratio of the two. Different lunar rock types are accurately distinguished based on different ratios. The present invention achieves accurate distinction of lunar rock types by successfully stimulating the annihilation radiation of typical rocks using a direct ground calibration method.

The application discloses a kind of proton, hydrogen atom double-charge state beam extraction device, its characteristics are: in the trajectory of beam acceleration to extraction energy, there is proton, hydrogen atom double-charge state beam extraction device;The double-charge state beam extraction device is provided with stripping target and / or electrostatic deflection plate combined by stripping film of different thickness and different position, the different position stripping film is used to adjust the proportion of each component beam online, the different thickness refers to according to the demand of multi-charge state beam extraction, stripping film is set to different thickness;The different position refers to the trajectory of beam extraction, the front and rear position of the multiple stripping films is different and the radial position is different between each other.The application solves the problem that the prior art can only extract single-charge state beam, and can only adjust the total flow intensity of each charge state beam online, but cannot adjust the flow intensity of each charge state beam respectively.