135 results about "Nuclear reaction" patented technology

A structure and process for containing a nuclear reaction is disclosed. The structure and process may involve a nuclear containment structure including a plurality of metallic rings stacked axially to form the nuclear containment structure, the nuclear containment structure being configured to: mitigate, by using a physical barrier, the movement of radionuclides from inside a containment structure to a surrounding space; shield, by varying the alloy properties throughout the containment structure, an exterior of the containment structure from radiation produced inside of the containment structure; regulate, by transferring thermal energy, a temperature within the containment structure; regulate, by storing thermal energy, the temperature within the containment structure; shield, components within the nuclear containment structure from kinetic events external to the nuclear containment structure; and shield, the external environment, from kinetic events within the nuclear containment structure.

The invention discloses an element analysis device based on a high-yield DD neutron generator. The device is composed of a neutron source item system, a neutron shielding collimation wall, a detector shielding protection system, a detected sample system, a signal acquisition system and a data analysis system. A neutron beam is generated through (D, D) nuclear reaction and irradiates a sample after passing through a neutron moderation layer and a shielding collimation wall, so that the sample generates instant characteristic gamma rays. A shielding protection system with unique design effectively reduces background gamma ray interference and electromagnetic interference, and ensures that the detector accurately collects sample signals. By matching with an advanced signal acquisition and analysis system, the element components and content of the sample can be analyzed at high precision. In addition, the device can be combined with a neutron imaging system to obtain sample structure information. The method has great application potential in the fields of industrial production, scientific research and detection and the like, and can meet the requirements of high-precision element analysis on small-size samples.

The invention discloses a GPU accelerated multi-particle coupling Monte Carlo calculation method and device. The method comprises the following steps: asynchronously migrating geometric material parameters subjected to CPU serial processing and a basic database to a pre-allocated memory space in a GPU; operation parameters of the GPU are determined, and Monte Carlo simulation of the multi-particle coupling transportation process is realized in the GPU based on the operation parameters and the neutron nuclear reaction database; on the basis of an atom addition function of a CUDA parallel computing architecture, energy transfer data, obtained through Monte Carlo simulation, of particles and voxel grids in a multi-thread environment is efficiently summarized, energy deposition of the particles is determined, and a high-resolution three-dimensional energy deposition spatial distribution data set is generated. According to the method, high precision can be maintained, and meanwhile, the parallel computing capability of the GPU is fully utilized to realize multi-particle coupling transportation synchronous simulation, so that the computing efficiency of a complex radiation field is improved, and the dual requirements of different fields on high precision and real-time performance are met.

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

The invention relates to the technical field of steel smelting scrap steel briquette treatment, and particularly provides a neutron generator-based scrap steel briquette component online detection device and method. Neutrons generated through nuclear reaction of a neutron generator are absorbed and activated with elements such as Fe in the scrap steel, gamma rays with characteristic energy are emitted, then the energy intensity of the gamma rays is observed, contrasted and calibrated from the response of a detector, and therefore the content composition and the content proportion of all the elements, mainly the Fe element, in the scrap steel briquette are calculated, analyzed and determined. The device effectively avoids the low-quality employment risk in the detection of the scrap steel briquettes, solves the problems that the detection of the internal quality of the scrap steel briquettes is difficult, time-consuming and labor-consuming, remarkably improves the working efficiency and effect, and has remarkable economic benefits and popularization prospects.

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 invention discloses a machine learning-based kernel data verification method, which comprises the following steps of: firstly, obtaining simulated effective proliferation factors and actually measured effective proliferation factors of a plurality of kernel experiment references, and calculating to obtain a difference value; 2, calculating nuclear data sensitivity characteristics of each experimental reference, wherein the nuclear data sensitivity characteristics comprise a sensitivity coefficient for a nuclear reaction cross section and experimental metadata; thirdly, constructing a machine learning model based on a random forest, and performing training by taking the kernel data sensitivity characteristics as input and the effective multiplication factor difference value as output; and finally, carrying out model feature importance analysis, and identifying kernel data sensitivity features which have significant influence on effective proliferation factor differences. The nuclear data verification method based on machine learning is established for the first time, and is used for identifying potential defects in nuclear reaction data or deviation of experimental references.

The invention relates to the technical field of boron neutron capture therapy, in particular to a dose verification device for boron neutron capture therapy. The objective of the invention is to solve the technical problem that dose distribution of tumor tissues and surrounding thereof cannot be accurately measured. To this end, the dose verification device of the present application comprises: a box; the die body assemblies move in the incident direction of the neutron beam and are arranged in a stacked mode; the die body insertion plate comprises a tumor tissue simulation positioning area containing boron-10 with a first concentration and / or a normal tissue simulation positioning area containing boron-10 with a second concentration, and the first concentration is greater than the second concentration; the dose detection module is used for detecting distribution data of secondary particles generated after the boron-10 and neutrons are subjected to nuclear reaction; and the data processing module is used for acquiring the distribution data and determining the dose distribution in the die body assembly according to the distribution data. According to the application, the difference of the boron-10 concentration of the tumor tissue and the normal tissue can be better simulated, and the dose distribution of the tumor tissue and the surrounding thereof can be more accurately measured.

This invention discloses a firecracker-style controlled nuclear fusion and fission synergistic power generation device and method. The power generation device includes a fission-fusion reaction system, a circulating cooling system, and other accessories. The fission-fusion reaction system includes a neutron gun, fuel spheres, a fuel sphere storage and delivery device, and a vacuum reactor. The circulating cooling system includes a circulating fan, a voltage regulator, a steam turbine, a steam generator, delivery pipelines, and a water pump. Other accessories include an energy storage and control system and a vacuum pump. This invention innovatively integrates the start-up mechanism, drawing on the firecracker-style multi-reactor relay concept, combining nuclear fission and nuclear fusion. It utilizes the high temperature and pressure generated by nuclear fission to start nuclear fusion, reducing start-up difficulty and cost. Simultaneously, it efficiently converts and utilizes energy, employing helium for heat transfer. Helium's high thermal conductivity, low density, high specific heat capacity, and chemical inertness allow it to effectively carry away the heat stored in the phase change microspheres, comprehensively collecting and converting nuclear reaction heat energy, thus improving energy conversion efficiency.

The invention discloses a semiconductor neutron detector, a preparation method and a neutron flux measuring device, and relates to the field of neutron detection.The semiconductor neutron detector sequentially comprises an ohmic electrode, a substrate, a buffer layer, an epitaxial layer and a Schottky electrode from bottom to top; the substrate, the buffer layer and the epitaxial layer are all made of 4H-SiC; when the semiconductor neutron detector detects neutrons, the neutrons and the epitaxial layer are subjected to nuclear reaction, electron hole pairs excited by neutron energy deposition sequentially pass through the buffer layer and the substrate from the epitaxial layer to the ohmic electrode, and the ohmic electrode outputs neutron current signals which are converted into voltage signals in the sampling circuit so as to perform neutron detection. By adopting the characteristics of high hardness, high thermal conductivity, wide forbidden band and high displacement threshold energy of the 4H-SiC material, the high-fluence-rate neutron flux can be measured in real time, and the reliability and stability of the semiconductor neutron detector are improved.

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

A method and apparatus for producing radioisotopes. The method includes generating fast neutrons by irradiating a neutron producing target with a deuteron beam from a deuteron accelerator. These fast neutrons directly irradiate a first sample. The fast neutrons that pass through the first sample undergo multiple-scattering by a neutron scattering material made of a light element positioned around both the neutron producing target and the first sample. This arrangement generates various radioisotopes simultaneously in large amounts from both the first sample and a second sample through nuclear reactions. The method enables production of multiple radioisotopes in a single process for applications in medicine, research, education, agriculture, and industry.

The application discloses a core model correction method and device based on data assimilation, and equipment, the method can change the characteristics of the power level of each component in the core by adjusting the characteristic parameters, and the accuracy of the core theoretical model after correction in simulating the theoretical power level of the component can be improved by parameter assimilation of the parameter values of the characteristic parameters in the core theoretical model; and if at least one of the first characteristic parameters which do not change with the nuclear reactor unit operation is corrected in the first i-1 core theoretical model correction processes, it is proved that the first characteristic parameters at each component in the i-1 corrected core theoretical model have reached balance and solidification, interference of the parameters in the i correction process can be avoided, and the accuracy of the core theoretical model after the i correction in simulating the theoretical power level of the component can be improved.

The invention relates to the technical field of nuclear, in particular to a device for detecting selenium content in fruits, which comprises a D-D neutron generator and a measuring chamber, the D-D neutron generator generates neutrons, the neutrons in the measuring chamber enter a sample to generate nuclear reaction with atomic nucleuses in the sample in the measuring chamber, and the neutrons in the measuring chamber are generated; after the atomic nucleus of the measuring chamber is activated, instant gamma rays and delayed gamma rays are released; the high-purity germanium detector in the measuring chamber receives delayed gamma rays of all elements in the sample in the measuring chamber and converts each gamma photon into an electric pulse signal; the multichannel analyzer is used for converting the electric pulse signals of the measuring chamber into digital signals, dividing channel addresses according to the size of the digital signals, counting the pulse number and forming a gamma ray energy spectrum; and the computer in the measuring chamber calculates the selenium content in the sample in the measuring chamber through the gamma ray energy spectrum in the measuring chamber. The method has the advantages of low detection limit, small error and high measurement result precision, and can quickly realize the detection of the selenium content in the fruits.

The invention discloses a nuclear rod power generation device, the nuclear rod power generation device comprises a nuclear fuel device, a neutron source device, a control assembly and a water pipe device, the nuclear fuel device is arranged in the water pipe device, and the water pipe device comprises a water inlet and a water outlet; the nuclear fuel device comprises an inner sleeve and an outer sleeve, the inner sleeve is arranged in the outer sleeve, the two ends of the inner sleeve and the two ends of the outer sleeve are connected in a sealed mode, a vacuum cavity is formed between the inner sleeve and the outer sleeve, and nuclear fuel coatings are arranged on the outer side of the inner sleeve and the inner side of the outer sleeve. The neutron source device is arranged on the inner side of the inner sleeve through a guide pipe, and the control assembly adjusts the position of the neutron source device in the guide pipe. The invention provides a nuclear rod power generation device which adopts a safe and miniaturized nuclear reaction technology and can replace a huge nuclear reactor.

The invention relates to a cyclotron which enables the production of α- or β-emitting radionuclides. The cyclotron, with a magnetic periodicity of 3, comprises three accelerating cavities connected to the centre, thus not requiring phase control between the cavities, forming a single high-frequency resonator. The six accelerating gaps per turn enable rapid acceleration (the angle ϕ between the accelerating gaps of each cavity being approximately 30°) which is essential for acceleration at the third and sixth harmonics. This cyclotron preferably has an injection system (31) supplied by different types of ion sources, making it possible to efficiently accelerate charged particles having Z / A ratios equal to 1 / 2 and to 1 / 4. The cyclotron may also have stripping extraction means positioned in the cyclotron so as to extract the charged particles and double their state of charge. These particles enable a set of nuclear reactions for producing α-emitting radionuclides.

The invention discloses a Beta radioactive isotope coating and magnetic confinement enhanced air-breathing electric propulsion ionization method. The method is characterized by comprising the following steps: selecting a plasma generation assembly without electrode discharge; the ionization is enhanced by adopting Beta radioactive isotope; arranging a magnetic field in the beta ray radiation direction to carry out magnetic field constraint; by dynamically adjusting the magnetic induction intensity and regulating and controlling the plasma state and the ionization rate, the Beta radioactive isotope (such as nickel-63) is creatively adopted, and the device has the advantages that the service life is long, the protection requirement is low, and mechanical compression and heating cannot induce nuclear reaction. And the requirement on the activity of the radioactive source is fundamentally reduced, so that the material cost and the safety risk are greatly reduced, and the practicability and the safety of the electric propulsion system are improved.

The invention discloses a neutron-gamma mixed radiation screening method based on a radiation response signal. The neutron-gamma mixed radiation screening method depends on a nano-coating CMOS sensor neutron measurement system. The neutron measurement system of the nano-coating CMOS sensor comprises a detector, the detector comprises a CMOS sensor; a LiF thin film is attached to the light-sensitive surface of the CMOS sensor; the method comprises the following steps that a part of neutrons enable the CMOS sensor to generate a radiation response signal A; the other part of neutrons and 6Li are subjected to nuclear reaction to generate alpha rays and tritium ions, so that the CMOS sensor respectively generates a radiation response signal B and a radiation response signal C; the gamma ray enables the CMOS sensor to generate a radiation response signal D; and according to the difference of the four radiation response signals in morphology and / or gray values, discriminating the neutron-gamma mixed radiation field. The detector formed by combining the LiF film and the CMOS sensor is used for discriminating a neutron-gamma mixed radiation field and can be used for monitoring nuclear leakage of a reactor.

The invention provides controllable nitrogen-hydrogen nuclear fusion equipment. The controllable nitrogen-hydrogen nuclear fusion equipment comprises a hydrogen nuclear particle generation device, a nitrogen nuclear generation device, a convolution migration particle accelerator and a focusing reaction field, the hydrogen nuclear particle generation device is provided with a hydrogen nuclear particle outlet, and the hydrogen nuclear particle outlet conveys hydrogen nuclear particles into the rotary migration particle accelerator; the rotary migration particle accelerator comprises a straight line section and an arc section, the hydrogen nuclear particles sequentially penetrate through the straight line section and the arc section to increase the speed, and the hydrogen nuclear particles with the increased speed are conveyed to the focusing reaction field; the nitrogen nuclear particle outlet conveys low-speed nitrogen nuclear particles into the focusing reaction field; the hydrogen nuclear particle beam with the increased speed and the low-speed nitrogen nuclear particle beam are converged towards the center of the focusing reaction field to generate nuclear reaction. According to the cyclotron migration particle accelerator, through the synergistic effect of the linear section and the arc section, hydrogen nucleus particles are accelerated through an electric field, meanwhile, the particles are deflected in the arc section, and repeated acceleration is achieved.

The application provides a fuel and a method for increasing the neutron source intensity of a nuclear reactor, wherein the abundance of O in the fuel is 1% to 50% 18 O is 1% to 50%, and alpha particles and the enriched 18 O can significantly enhance the initial neutron source intensity of a nuclear reactor core in a pressurized water nuclear power plant, and help to improve the start-up performance and reduce the dependence on external neutron sources. In the passive start-up mode without using an external neutron source, the application improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant. 18 O in the fuel, and improves the isotope abundance of O in the fuel, and improves the (alpha, n) reaction neutron source in the nuclear reactor core in the pressurized water nuclear power plant.

An arylboron compound, its preparation method, applications, and pharmaceutical compositions are disclosed for tumor imaging. The compound of formula (I) exhibits high fluorescence quantum efficiency through intramolecular charge transfer. The compound of formula (I) synthesized in this invention can be linked to different antibodies via Q3 at certain concentrations, allowing for precise targeting of corresponding tumors based on the antibody. This type of boron drug formulation can be used in boron neutron capture therapy to kill tumor cells. It exhibits better killing effects; the compound of formula (I) targets tumor cells through antigen-antibody interaction. After the boron-10-containing drug accumulates at the tumor site, neutron radiation triggers a nuclear reaction releasing alpha particles and... 7 Lithium particles kill cells; the range of these two particles is approximately 10 μm. High-energy-density heavy ions disrupt the DNA double helix structure in tumor cells, causing irreparable cell death. Simultaneously, the 10 μm distance avoids damage to normal cells and tissues.

An ion implantation system includes a spectroscopy-based safety system for nuclear reaction detection. A spectra analysis and safety system are disclosed herein. Associated methodology for use with the system includes processing data received from photon energy resolving spectrometers in order to identify detected photon energy, and alert the operator to the same and / or shutdown the system.

The invention discloses a neutron sensitive scintillator probe with a high counting rate, a neutron detector and a preparation method, and relates to the technical field of neutron detectors. The neutron sensitive scintillator probe is different from a traditional layered or array structure, a neutron sensitive material and a scintillation luminescent material which are uniformly mixed are adopted as a probe main body, the neutron sensitive material and incident neutrons are subjected to nuclear reaction to generate secondary charged particles, the secondary charged particles are energy-deposited in the scintillation luminescent material, and the neutron sensitive material and the scintillation luminescent material are separated from each other. The scintillation luminescent material is excited to emit scintillation light, so that the signal transmission time is reduced, the counting rate of the detector is improved, and the detector has the advantages of strong anti-interference capability and small size.

The invention discloses a reactor vacuum reflective thermal insulation device and nuclear reaction equipment. The reactor vacuum reflection heat insulation device comprises a shell, a reactor core assembly and a heat insulation reflection part, the shell is provided with a containing cavity and a vacuumizing opening, the vacuumizing opening is formed in the side wall of the shell, and the vacuumizing opening is used for vacuumizing the containing cavity; the reactor core assembly is arranged in the accommodating cavity, and a gap is formed between the reactor core assembly and the inner wall of the accommodating cavity; and the heat insulation reflection part is arranged between the reactor core assembly and the inner wall of the accommodating cavity. The low-emissivity and high-reflectivity radiation heat insulation mode of the heat insulation reflection part and the double heat insulation mode of combining the heat insulation reflection part with the vacuum interlayer are utilized, an obvious temperature gradient is formed in a compact space, the temperature of the outer surface of the shell of the pressure-bearing container is effectively reduced, and heat leakage of the reactor core assembly is reduced.

The invention discloses a nuclear reaction cross section data generation method and system based on machine learning. The nuclear reaction cross section data generation method based on machine learning comprises the following steps: acquiring data of nuclide characteristic indexes; the data of the nuclide characteristic indexes are used to predict a nuclear reaction cross section by using a pre-trained ensemble learning model, the ensemble learning model comprises a plurality of base learners and a secondary model, and the base learners are used to predict according to the nuclide characteristic index data; the secondary model is used for integrating the prediction results of the base learners to obtain the nuclear reaction cross section. The invention aims to optimize the generation efficiency and accuracy of nuclear reaction cross section data by combining various machine learning and deep learning technologies.

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.

A pulse type alpha particle time flight spectrometer is characterized in that a fixing ring, an aluminum foil, a scintillator, a light guide and a light guide optical fiber connector are integrated together and then are connected with an adapter flange, an optical fiber is fixed at the other end of the light guide optical fiber connector, and the optical fiber, a high-voltage power supply, an oscilloscope and a signal generator are connected to PMT corresponding ports of an MCP-PMT8; according to the invention, the scintillator detector is combined with the gated micro-channel photomultiplier tube, the interference of a complex environment on the detection of nuclear reaction products is effectively inhibited by using the time difference between electrons and gamma light and charged particles and using a gating technology, and the detection in a strong electromagnetic environment is realized; the influence of strong electromagnetic interference generated in a strong laser environment on an experiment result can be avoided; the detector can be applied to detection of particle beams with extremely narrow pulse width and extremely high instantaneous intensity, and has the advantages of simple structure and capability of quickly giving a measurement result.

Disclosed is a micro nuclear reactor that includes a core filled with nuclear fuel and moderator which are formed of particles, a heat pipe inserted in the core and transferring outwards heat generated by a nuclear reaction, and a power converter receiving heat from a condenser of the heat pipe and converting thermal energy into electrical energy.

The invention relates to the technical field of positron annihilation lifetime measurement, and provides a positron annihilation lifetime spectrum measurement device, which comprises an alpha particle generation device, an alpha particle detection device, a gamma ray detection device and a lifetime measurement device, and is characterized in that the alpha particle generation device generates alpha particles and first gamma rays through nuclear reaction; the first gamma ray enters a to-be-detected sample, and positron annihilation occurs in the to-be-detected sample to emit a second gamma ray; the alpha particle detection device is used for detecting alpha particles and generating an initial signal; the gamma ray detection device is used for detecting a second gamma ray and generating a termination signal; the lifetime measuring device is used for acquiring a time interval between the start signal and the termination signal to generate a positron annihilation lifetime spectrum. As alpha particles are easy to shield and the detection efficiency is higher than that of gamma rays, the alpha particles are used as initial signals, so that the screening efficiency of effective events and the overall counting rate of the system can be greatly improved, and the positron annihilation lifetime spectrum has good signal-to-noise ratio and measurement accuracy.

The invention relates to the technical field of nuclear reaction safety facilities, and provides a multi-stage suppression water tank and method.The multi-stage suppression water tank is arranged in a containment and comprises a first-stage suppression water tank to an Nth-stage suppression water tank, the water space of the first-stage suppression water tank communicates with the inner space of the containment through a first-stage suppression pipe, and the water space of the second-stage suppression water tank communicates with the inner space of the containment through a second-stage suppression pipe; the water space of the Nth-stage pressure suppression water tank is communicated with the air space of the (N-1) th-stage pressure suppression water tank through a middle pressure suppression pipe, and N is an integer greater than or equal to 2. Water vapor entering the pressure suppression water tank is fully condensed, the condensation efficiency is improved, and the pressure suppression capacity of the pressure suppression water tank is improved; and the water vapor is fully condensed, so that the volume of the suppression water tank can be greatly reduced.