62 results about "Nuclear reaction" patented technology

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

The 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 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 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.

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.

This application relates to the field of nuclear reaction control using neutron-absorbing materials, specifically to a reactivity control assembly and reactor suitable for a reactor, including a neutron absorber, a conduit, a drive mechanism, and a sealing connector. The conduit is located radially outside the core assembly, and the centerline of the portion located inside the reactor vessel has a curvature variation. The neutron absorber is disposed within the conduit for absorbing neutrons. The drive mechanism is configured to drive the neutron absorber to move along the centerline of the conduit within the conduit to control the reactivity of the reactor. The sealing connector is configured to connect the drive mechanism and the conduit, and to seal the drive mechanism and the conduit in the reactor. The neutron absorber is configured to adapt to the curvature variation of the conduit at different positions along the centerline when moving within the conduit. The reactivity control assembly provided in this application facilitates reactor miniaturization by allowing the centerline of the portion of the conduit located inside the reactor vessel to have a curvature variation.

To reduce monitoring cost in a nuclear system.SOLUTION: A nuclear system comprises: a nuclear reactor core; a heat conductor that conducts heat which is generated by nuclear reaction of nuclear fuel in the nuclear reactor core to outside by means of a cooling medium; a reactivity control device that has a plurality of control drums in which a neutron absorption part arranged outside the nuclear reactor core to absorb neutrons is provided; a state detector that detects an operational state of a nuclear reactor; and an analysis unit that reproduces the operation state of the nuclear reactor in a virtual space using a virtual model of the nuclear reactor on the basis of a detection result of the state detector.SELECTED DRAWING: Figure 3

Disclosed is a neutron capture therapy apparatus. The neutron capture therapy apparatus is used for irradiating a neutron beam with a preset neutron dose to an object to be irradiated. The neutron beam enters the object and undergoes a nuclear reaction with boron in the object. The neutron capture therapy apparatus includes a correction system for correcting the preset neutron dose.

The application discloses a multi-nucleus neutron nuclear reaction data verification method and device based on deep learning, comprising the following steps: determining a target nucleus to be evaluated, and obtaining multi-dimensional physical characteristic data of the target nucleus from a preset evaluation nuclear database and an experimental database; performing physical perception preprocessing and feature splicing on the multi-dimensional physical characteristic data to obtain a physical characteristic vector of the target nucleus; constructing and training a nuclear data correction model with uncertainty quantification capability; determining evaluation cross-section data and uncertainty data of the target nucleus according to the nuclear data correction model and the physical characteristic vector, and encapsulating the evaluation data of the target nucleus according to the evaluation cross-section data and the uncertainty data; verifying the evaluation data based on particle transport simulation, and optimizing the evaluation nuclear database according to the verified evaluation data. The application improves the efficiency and reliability of neutron nuclear reaction data evaluation and verification, and can be applied to the technical field of data processing.

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 present invention relates to the field of controlled nuclear fusion in nuclear energy applications. The title of the present invention is a positive-ion circular-collision nuclear fusion reactor. The technical problems to be solved by the present invention are: the nuclear fusion reaction times are short and the energy gains Q are less than 1. Our technical solution is: using an accelerator to accelerate hydrogen isotope positive ions to (0.1-3) Mev, and then inducing nuclear fusion reactions by circular collision. In the past, it was believed that the probability of inducing nuclear fusion by collision was less than 0.0001. We simultaneously employ five technical schemes to solve the problem of low probabilities of positive ion collision-induced nuclear reactions: 1. using the accelerator to accelerate the positive ions to (0.1-3) Mev; 2. using circular collision to induce nuclear fusion; 3. enabling collision in a collision area having a large cross section; 4. enabling collision in a long collision area; and 5. using a plurality of sets of electromagnetic lenses to focus ion beams to increase the ion density. In the present invention, energy generated by nuclear fusion is converted into heat energy in an energy conversion area, and then high-pressure steam is generated for power generation.

The invention discloses a boron concentration monitoring device, a monitoring system and a monitoring method in neutron therapy, and relates to the technical field of neutron therapy. A carrier with a circular plane is arranged, scintillator detectors with circular planes are arranged in an array in the carrier, and when an accelerator neutron source outputs neutron beams to irradiate a target, the scintillator detectors are arranged in the carrier; nuclear reaction is carried out on neutrons and boron in a target to generate gamma rays, and the scintillator detectors arranged in an array uniformly receive the gamma rays generated in the area reflecting the gamma rays in the whole neutron beam irradiation area without dead angles, so that dead zones which cannot be covered by a single detector when the single detector receives the gamma rays can be greatly reduced; and then the distribution of the boron concentration is determined by determining the scattering angle and energy of the gamma ray, and the optimal detection position is determined according to the distribution of the boron concentration at different positions, so that the optimal detection position can be quickly and accurately found, and the overall detection efficiency is greatly improved.

The invention discloses a method for extracting prenuclide and preparing medical alpha isotope on a large scale based on monazite discharged waste slag. According to the method, high-value conversion of radioactive waste is realized by comprehensively utilizing the monazite waste slag. The alpha isotope is used as a core raw material for extracting preposed nuclide, so that the environmental harm of radioactive waste residues is reduced, waste is turned into wealth, and a stable raw material source is provided for preparing the medical alpha isotope. A complete technical chain for extracting the medical alpha isotope 225Ac / 212Pb from the monazite waste slag containing 226Ra and 228Ra is constructed, and efficient output of high-value nuclides is achieved. 226Ra and 228Ra in the discharged waste slag are obtained through a step-by-step extraction process flow of a coarse radium product and a fine radium product, a radium target of an ECANS device is manufactured, and hot medical alpha isotopes such as 225Ac, 212Pb and the like can be prepared on a large scale by utilizing a photo-nuclear reaction. According to the preparation mode, the utilization rate of the discharged waste slag is increased, and the requirement of radioactive diagnosis and treatment on the medical alpha isotope can be met.

Provided is a nuclear reactor unit that can reduce a temperature increase in a reactor core at the occurrence of an abnormality with a simple structure. Included are a reactor core having radioactive fuel and causing the radioactive fuel to cause a nuclear reaction and a nuclear reactor vessel housing the reactor core and hermetically sealing the reactor core. The nuclear reactor vessel includes an inner shroud covering the entire periphery of the reactor core and an outer shroud covering the entire periphery of the inner shroud. A first space formed by the outer shroud and the inner shroud is in a vacuum condition. The inner shroud includes a main body and a communicating part placed in part of the main body and communicating the first space to a second space, which is a space inside the inner shroud, when the reactor core reaches a threshold temperature or higher.

The present application relates to a kind of neutronics calculation uncertainty quantification method, system, equipment and medium, belong to neutronics calculation field.The method includes: based on the covariance information in nuclear data evaluation library making nuclear data covariance library;Using direct numerical perturbation method calculates the sensitivity coefficient of nuclear reaction cross section to spallation neutron source;According to the nuclear data covariance library and the sensitivity coefficient, the uncertainty of spallation neutron source is calculated;According to the nuclear data covariance library and the uncertainty of spallation neutron source, using Latin hypercube sampling method is sampled to generate calculation sample;Based on the calculation sample, the ADS neutronics calculation result is obtained by executing ADS neutronics calculation;The uncertainty of the ADS neutronics calculation result is determined by performing mathematical statistics analysis to the ADS neutronics calculation result.The present application improves the calculation efficiency and calculation accuracy of the uncertainty of ADS neutronics calculation.

To provide an ion source and an accelerator, as well as a method for generating ions and accelerating those ions in the ion source.SOLUTION: A nuclear reaction generation device includes a chamber configured to contain gas and include a target. The nuclear reaction generation device also includes a filament provided within the chamber and a voltage source configured to apply a first positive voltage to the filament relative to the chamber. The first positive voltage is configured to heat the filament to a temperature that causes thermionic emission and generates multiple thermions. The multiple thermions are configured to ionize the gas and generate positive ions in the chamber. The target is configured such that nuclear reactions occur when the positive ions interact with the target.SELECTED DRAWING: Figure 1

Provided are a nuclear reaction generating apparatus and a nuclear reaction generating method that have good energy efficiency, and a method for producing He-3 that does not generate radioactive substances. The nuclear reaction generating apparatus is composed of a cooling unit (2), a container (3), a heat generating body (4), a heater (5), a thermocouple (6a), a thermocouple (6b), a hydrogen gas tank (11), and a heater control unit (12), wherein the cooling unit (2) houses a heat medium (7). The heat medium (7) extracts the heat of the heat generating body (4) via the container (3). According to the method for producing He-3, an amorphous alloy composed of Cu, Ni, and Zr is fired in the atmosphere at a prescribed temperature of 400 to 500°C, a resultant alloy oxide is pulverized, and then an alloy oxide that has occluded hydrogen in a vacuum container is obtained and fired at 400 to 500°C. Then, by heating the alloy oxide that has occluded hydrogen and been fired in a nitrogen atmosphere or an argon atmosphere, with isochronal temperature rise to 900°C or higher, He-3 held in the alloy oxide is extracted.

The present invention relates to a nuclear target (1), a method for inducing a nuclear reaction and a device capable of inducing a nuclear reaction. According to the present invention, the nuclear target (1) comprises a cavity (12) in which incident nuclear particles (3) are deposited. In the cavity (12), the incident nuclear particles (3) interact with precursors (21 and / or 22 and / or 23) or the incident nuclear particles (3) are elastically scattered in isotopes (4). Thus, the nuclear target (1), method or device provides a more efficient induction of nuclear reactions and provides a higher yield of radioisotope production. In another embodiment, the nuclear target (1) can be used as a means used for nuclear waste transmutation or as a means for sustainable exothermic nuclear reactions.

This invention relates to a method for generating a high-purity Ac-225 radioactive beam based on an online isotope separator. A high-energy proton beam with an energy of 100 MeV is generated using a cyclotron accelerator. This high-energy proton beam is transmitted to an ISOL target chamber and bombards a thorium carbide target within the chamber, causing a nuclear reaction. Atoms produced in the nuclear reaction escape from the target and interact with a specific wavelength of incident laser light, resulting in stimulated ionization. The stimulated ionized radioactive nuclear beam is extracted by a high-voltage ion source and then transmitted via a beam transport system to a pre-analytical magnet. The radioactive nuclear beam undergoes preliminary separation by the pre-analytical magnet. After preliminary separation, the radioactive nuclear beam is further accelerated by a high-voltage accelerator tube and then further separated by the main analytical magnet to improve the purity of the beam. Compared with radiochemical separation methods, this invention offers higher separation efficiency and a shorter separation cycle, yielding Ac-225 with a purity exceeding 99%. Further purification is expected to meet the requirements of clinical trial standards.

The invention provides a secondary source item generation method for neutron capture therapy. The traditional method has the problems of low calculation efficiency, insufficient precision and the like during neutron capture therapy dose evaluation. The method comprises the following steps: firstly, establishing a three-dimensional model of the neutron capture therapy device based on a Monte Carlo particle transport program, and recording secondary particle information of a region to be set as a secondary source item; reconstructing a model, and reasonably dividing energy groups, angles, spatial distribution and the like to make secondary source items; and finally, compiling a secondary source item according to a program source item format for subsequent calculation. The method is suitable for handling the particle transport problem of complex geometric structure or low nuclear reaction particle yield, can accurately describe the radiation field to the maximum extent, can overcome the problems of low direct simulation efficiency and the like caused by low (p, n) reaction secondary neutron yield, improves the calculation speed and precision, and provides a better dose evaluation scheme for neutron capture therapy.