281 results about "Neutron" patented technology

The invention relates to the technical field of yield control, in particular to a neutron generator yield control method and system. The method comprises the following steps: establishing a polynomial model by using historical yield data to predict a target efficiency attenuation factor; dynamically determining neutron event boundaries in the pulse integral value and the pulse width two-dimensional characteristics based on the attenuation factor, and counting the neutron event boundaries; the yield deviation and the change rate are calculated, and when the deviation exceeds a threshold value, feedforward compensation is carried out on the target yield; and selecting a three-dimensional lookup table, an input deviation, a change rate and a current high voltage according to the interval to which the attenuation factor belongs, and cooperatively determining the adjustment amount of the ion source current and the accelerator high voltage. According to the scheme, the measurement and control problems caused by aging of the target piece can be solved, and the precision, the response speed and the long-term stability of yield control are improved.

The invention relates to an intelligent design method of a radiation shielding material based on cross-scale error feedback lock step, which comprises the following steps: determining a material component set and acquiring an atomic-scale graph structure of the material component set, and extracting intrinsic performance parameters such as heat conductivity and attenuation coefficient through an atomic-scale prediction module; and then, constructing a design variable vector in combination with a multi-physical field condition, calculating equivalent performance parameters of the composite material, establishing a cross-scale lock step mechanism, and triggering a molecular dynamics and Monte Carlo recalculation module to carry out correction when the deviation between a predicted value and a mesoscopic recalculation result exceeds a limit. Based on the correction parameters, a candidate material scheme is generated by using a multi-objective optimization algorithm; and performing gamma-ray and neutron shielding performance simulation on the candidate schemes through a Monte Carlo radiation transfer model accelerated by a deep neural network, and comparing with an experimental result to realize self-adaptive material design driven by cross-scale errors. According to the method, the design precision and efficiency of the radiation shielding material are remarkably improved.

The invention provides a doped yttrium hydride neutron moderation material and a preparation method and application thereof, and belongs to the technical field of radiation shielding materials. At least one of samarium, europium and gadolinium is doped in yttrium hydride in the form of hydride, and the mass ratio of metal yttrium to metal gadolinium to metal europium to metal samarium is controlled, so that the neutron moderation effect of the neutron moderation material can be improved. According to the invention, at least one of gadolinium hydride, europium hydride and samarium hydride is mixed with yttrium hydride under the protective atmosphere, so that the mass content of each element in the doped yttrium hydride neutron moderation material can be accurately controlled. According to the invention, the mixture is sintered and molded, and the sintering parameters of sintering and molding are controlled, so that the components of the mixture are sintered in a compact state, cracks generated by thermal expansion and cold contraction can be reduced, and the doped yttrium hydride keeps high density and has fewer cracks and defects.

A system and a method for a pulsed neutron logging tool. The pulsed neutron logging tool may include a pulsed neutron generator for generating one or more neutrons, one or more gamma ray scintillator detectors disposed in a detection area, a shielding block that separates the pulsed neutron generator from the one or more gamma ray scintillator detectors, and a shielding layer. The pulsed neutron logging tool may further comprise an information handling system communicatively connected at least in part to the pulsed neutron logging tool. The information handling system is configured to create a gamma ray spectrum from the one or more gamma rays detected by the one or more gamma ray scintillator detectors, remove a background from the gamma ray spectrum to form a peaks-only spectrum, and compare one or more peaks-only elemental standards to the peaks-only spectrum to determine an elemental weight and yield.

The invention discloses a composite shielding collimator suitable for a complex mixed radiation field, belongs to the technical field of radiation shielding and measurement, and mainly solves the problems of low signal-to-noise ratio, high space background and mixed energy spectrum caused by the mixed radiation field of high-energy neutrons, gamma rays and the like in a fusion device and the problem that traditional equipment is heavy and difficult to flexibly adjust. The composite shielding collimator adopts a cylindrical shielding structure formed by aluminum oxide, boron-containing polyethylene, boron carbide and lead from outside to inside, and background interference and secondary radiation are remarkably inhibited by moderating and absorbing neutrons step by step and effectively shielding gamma rays; the neutron and gamma ray detector is integrally integrated on a rotatable supporting mechanism, unification of excellent radiation shielding performance and detection flexibility is achieved, and the neutron and gamma ray detector is mainly used for high-precision neutron and gamma ray diagnosis in complex radiation environments such as a magnetic confinement fusion device.

The invention relates to a moderator of a compact single-ball neutron spectrometer, and the moderator is characterized in that an inner layer is of a cylindrical structure, and a plurality of thermal neutron detectors are installed in the inner layer; the thermal neutron absorption layer sleeves the outer side of the inner layer and is made of boron-containing polyethylene; the scattered neutron moderation layer sleeves the outer side of the thermal neutron absorption layer; the inner layer comprises a detector placing block and a thermal neutron absorption block, and the thermal neutron absorption block is provided with a storage groove; a plurality of thermal neutron detectors are placed in the detector placement block along the axis direction, the first thermal neutron detector is placed in the storage groove, and the thermal neutron absorption block is made of boron-containing polyethylene; the diameter of the inner layer is 8 cm, the outer diameter of the thermal neutron absorption layer is 14 cm, and the outer diameter of the scattered neutron moderation layer is 20 cm. The purposes that the size is controlled by controlling the diameter of the cylindrical structure and the scattering shielding effect is enhanced by arranging the three layers of moderator structures in a sleeving mode are achieved, and therefore the technical effects that the moderator is small in size, convenient to transport and high in scattering shielding effect are achieved.

The invention provides a radioactive substance transportation monitoring system, and relates to the technical field of radioactive substance transportation safety monitoring. The radioactive substance transportation monitoring system comprises a transfer protection box and a monitoring unit integrated on the transfer protection box, and the monitoring unit is composed of a double-detector fusion module, a three-dimensional data linkage analysis module and an active emergency disposal module which are sequentially connected through a circuit. The double-detector fusion module comprises a GM counting tube and a scintillator detector which are arranged inside and outside the box so as to realize alpha, beta, gamma and neutron multi-nuclide coverage; the three-dimensional data linkage analysis module performs comprehensive judgment based on internal and external doses of the box, temperature and humidity and vibration data, and accurately identifies protection failure or article leakage; and the active emergency disposal module automatically starts gate closing and adsorption measures in an emergency. According to the system, the problems of monitoring blind areas, reduced protection performance, frequent false alarm, emergency passivity and the like are solved, and the transportation safety and the intelligent level are improved.

The invention relates to a neutron measuring device (1). The device (1) comprises a housing (90), a high-density polyethylene block (10) in the housing (90), a shell made of neutron-absorbing material (20) integrated into the block (10), a first scintillation neutron detector (30) located inside the shell (20) and capable of emitting a signal proportional to the number of neutrons detected per unit of time, and a module (40) capable of converting the signal into a neutron count rate.

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.

The invention relates to a flight tube structure of a magnetic confinement fusion fast neutron spectrometer, and belongs to the technical field of magnetic confinement fusion fast neutron spectrometers. The invention aims to provide a flight tube structure of a magnetic confinement fusion fast neutron spectrometer aiming at the problems in the prior art, the flight tube structure comprises a plurality of flight tube sections which are connected in sequence, and a plurality of hollow cylindrical collimation blocks are arranged in the flight tube sections and are used for absorbing and collimating neutrons. According to the flight tube structure of the magnetic confinement fusion fast neutron spectrometer, flexible system building can be achieved, the system complexity is low, and the neutron absorption efficiency of different energy sections is higher.

The invention relates to the technical field of neutron measurement, and particularly discloses a multi-activation foil and method for measuring a neutron energy spectrum. The multi-activation foil comprises a shell and an activation sheet placed in the shell, and the activation sheet sequentially comprises Ni, Sc, Au, W, Cu, Pt, In, Zn and Fe from top to bottom. The activated foil can realize high-resolution measurement of a neutron spectrum in a very small space, has the characteristics of size miniaturization, wide energy response range, wide neutron fluence rate application range, controllable manufacturing tolerance, optimized material ratio and the like, and is suitable for neutron spectrum and neutron dose measurement of a small-scale region of a nuclear facility and neutron dose measurement of a small-scale region of a nuclear facility. The method can also be popularized and applied to fine dose field distribution measurement of a large-scale area of a nuclear facility, and provides accurate data support for safe operation, shielding verification and radiation protection of the nuclear facility.

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.

A plasma focus system for neutron production is disclosed that includes an electrode assembly having an inner electrode extending along a pinch axis from a discharge end to a focus end, and an outer electrode surrounding the inner electrode to define a plasma channel for receiving a gas containing neutronic fusion fuel. The system also includes a power supply unit for applying a discharge driving signal to the electrodes, which causes the gas to be ionized into a plasma current sheath at the discharge end that flows along the plasma channel to reach the focus end where the sheath collapses toward the pinch axis to form a plasma pinch that generates fusion neutrons. The inner electrode has a tapered tip at the focus end that is configured to increase a speed of the sheath sufficiently to reach a pinch temperature at which the fusion neutrons are predominantly of thermonuclear origin.

To prevent falling of a core during releasing without rotating a molding die.SOLUTION: A core manufacturing apparatus 1 includes a cavity 13, a molding die 10 having a through hole 14 passing toward the cavity 13, and an extrusion pin 22 which releases a core W from the molding die 10 in a state of inserted into the through hole 14, making a tip bite into an excess thick part of the core W molded by the cavity 13 and holding the core W. The molding die 10 is such a vertical split mold that a parting line extends in a vertical direction, and the extrusion pin 22 is moved to a horizontal direction vertical to the vertical direction.SELECTED DRAWING: Figure 3

The invention relates to the technical field of neutron measurement, and particularly discloses a thermoluminescence field dosimeter for measuring neutron energy spectrum.The thermoluminescence field dosimeter comprises a thermoluminescence field dosimeter body, and the thermoluminescence field dosimeter body comprises a front-end assembly, a rear-end assembly and a center assembly located between the front-end assembly and the rear-end assembly; the center assembly and the rear end assembly are detachably connected with the front end assembly. Wherein the distance between the front surface of the central assembly and the front surface of the front end assembly is 1mm, the distance between the front surface of the rear end assembly and the front surface of the front end assembly is 7mm, and the front surface of the central assembly and the front surface of the rear end assembly are respectively provided with a 6LiF thermoluminescence dosage piece and a 7LiF thermoluminescence dosage piece. The thermoluminescence field dosimeter is wide in neutron energy response range, covers 0.0253 eV-20 MeV, can be suitable for neutron energy spectrum measurement of nuclear facilities such as fission reactors, fusion reactors and medical accelerators, and is particularly suitable for measurement in measurement occasions with narrow spaces and large neutron field gradients.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

The invention relates to the technical field of nuclear reactor cores, and provides a reactor core adopting different hydrides for combined application, the reactor core comprises a plurality of fuel assemblies which are sequentially arranged in a zoning manner along the radial direction from the center to the periphery; part of the fuel assemblies simultaneously comprise uranium zirconium hydride fuel rods filled with uranium zirconium hydride fuel and uranium yttrium hydride fuel rods filled with uranium yttrium hydride fuel. Metal hydride fuel rods are introduced into the moderator-free reactor core, the reactor core neutron energy spectrum is slowed down, the reactor core fission reaction rate is increased, the reactor core critical mass is reduced, meanwhile, the equivalent nuclear density of uranium and hydrogen in different areas of the reactor core is adjusted in the mode that different hydride types are used in a combined mode, and reactor core power distribution is further flattened.

The application discloses a kind of fluid identification method and system of water-saturated hydrogen index contrast method, calculate reservoir matrix porosity;Electric imaging and double lateral data are combined to calculate rock fracture porosity, and sum matrix porosity to total porosity;Assume that bedrock reservoir pore is water-saturated, select the dynamic skeleton neutron value of the dense layer section of lowest porosity, high resistivity dynamic skeleton as fixed skeleton value, calculate the dynamic skeleton neutron value of the purpose layer in combination with total porosity;According to dynamic skeleton neutron value, calculate water-saturated hydrogen index of research interval;Water-saturated hydrogen index is compared with neutron actual logging value to calculate neutron difference value;In combination with gas production test data, the relationship between acoustic time difference and neutron difference value and the change relationship between matrix porosity and neutron difference value are analyzed using neutron difference value, and the relationship chart of quantitative identification gas-water layer is obtained.The method eliminates the influence of anisotropy, fracture occurrence and the like of bedrock lithology, highlights the characteristics of reservoir gas layer, and can more accurately identify the properties of reservoir fluid.

The invention discloses a monitoring device and an experimental device for a neutron poison layer in a spent fuel bearing device, and relates to the technical field of nuclear chemical engineering, the monitoring device comprises a first support and a second support, the bottoms of the first support and the second support are respectively provided with a moving device, and the first support and the second support are arranged in parallel at an interval; the radiation device is connected to the first support, the radiation end of the radiation device faces the second support, and the radiation end is provided with a first moderation layer; the detection device is connected to the second support, the detection device is provided with a second moderation layer, and a plurality of detectors are sequentially inserted into the second moderation layer. According to the technical scheme, the radiation device and the detection device are supported through the first support and the second support respectively, the radiation device and the detection device can move relatively through the moving device, and the monitoring device can flexibly monitor neutron poison layers at different positions of the spent fuel bearing device.

The invention provides a path planning method and system for cooperative ball change of a neutron multi-ball spectrometer, and relates to the field of data processing. In the method, a real contact condition is obtained by superposing an irradiation field, a temperature field and a structural vibration field in a three-dimensional model, an attitude evolution law of a sphere in an initial contact state is extracted, and a phase-locked cone region and a phase-locked circulation track are calibrated; and dividing a far area, an approaching area and a phase-locked window area in the multi-ball stacking area according to the distance, the approaching area and the phase-locked window area so as to generate a macroscopic approaching path. In the execution process, a sensor is used for detecting initial contact, and a phase-locked circulation track is superposed in a phase-locked time window, so that the posture of the ball tends to be a stable posture attractor; after phase locking is completed, amplitude is gradually reduced, clamping force is increased, and stable locking is achieved. And finally, a complete ball changing path plan is obtained by fusing the local phase locking path and the macroscopic approaching path. By implementing the technical scheme, the problem that the ball changing task is influenced by the attitude degradation uncertainty of the ball in the initial contact state is solved.

An absorber-reflector unit (100) for a nuclear reactor control drum, the absorber- reflector unit comprising a base plate (10), a neutron-reflecting material (20), and neutron-absorbing material (30); at least one shaft (40) connected to the base plate and passing through the neutron-reflecting material, the at least one shaft being coupled to the neutron-reflecting material such that when the at least one shaft is rotated the neutron-reflecting material is rotated; and at least one attachment member (50), the at least one attachment member being at least partially housed within both the neutron- reflecting material and the neutron-absorbing material so as to couple the neutron- reflecting material to the neutron-absorbing material.

Systems, devices, and methods for converting a raw neutron beam to a specified deliverable format having a targeted energy range, size, and direction are described. Embodiments of a neutron beam converter can include numerous regions based on location, function, dimension, and / or constituent material. The regions can include a central region, an intermediate region, a peripheral region, and a frontal region. Materials are also described.

The invention discloses a reflecting layer equivalent model determination method and device and a nuclear design calculation method and system, and relates to the technical field of nuclear industry. The reflecting layer equivalent model determination method comprises the following steps: acquiring an initial reflecting layer model of a reactor and a reactor core neutronics characteristic theoretical value; according to the theoretical value of the neutronics characteristic of the reactor core, adjusting initial information of the initial reflecting layer model so as to simplify the initial reflecting layer model and obtain a target reflecting layer equivalent model; according to the embodiment of the invention, the method can simplify the equivalent model of the reflecting layer under the condition that the theoretical value of the neutronics property of the reactor core meets the requirement, and further can guarantee that the calculation accuracy and calculation efficiency of a deterministic reactor core program meet the nuclear design requirement.

The application provides a neutron equivalent modeling method and device for high filling rate dispersion particles, and the method comprises the following steps: calculating the maximum outer radius of the equivalent particles; under the premise of keeping the core diameter of the particles unchanged, calculating the maximum compression ratio of the cladding layer of the particles; according to the set compression ratio, calculating the filling rate of the equivalent fuel element after the size of the cladding layer of the particles is compressed, wherein the set compression ratio is less than or equal to the maximum compression ratio; adjusting the density of the cladding layer material and the density of the matrix material to ensure the conservation of nucleon number of the cladding layer and the matrix material before and after the equivalent; and using a traditional modeling method to perform geometric modeling and neutron calculation on the equivalent fuel element. The application can effectively avoid the filling rate limitation of the random sequence increasing method, meet the modeling demand of random distribution of high filling rate dispersion particles, and realize reactivity equivalence and ensure the neutron calculation accuracy.

The invention discloses a tension-torsion multi-axial fatigue experiment device and method based on synchrotron radiation and neutrons. The experimental device comprises a base, a lower cavity, an acrylic / aluminum alloy projection window, an upper cavity, a supporting rod, a supporting plate, a hydraulic actuator, an upper connecting rod, a load sensor, an upper clamp, a multi-axial fatigue sample, a lower clamp, an angle sensor, a lower connecting rod, a torsion servo motor, a motor controller, an advanced light source receiver, an advanced light source entrance slit and the like. And performing macroscopic three-dimensional damage distribution characterization and microstructure evolution and damage evolution process experiments in the sample by penetrating the metal sample through X-rays and neutron beams. The method provides direct and reliable experimental data support for establishing a multi-axial fatigue theoretical model, revealing a material failure mechanism and engineering structure anti-fatigue design.

Molten salt nuclear reactor, of the fast neutron type with a safety vessel around the reactor vessel and a drain tank below the vessels. The invention relates to a nuclear reactor (1) comprising: - at least one nuclear reactor vessel (2) (1) filled with a molten salt fuel bath and provided with at least one outlet in its bottom; - another vessel (8), called the safety vessel, arranged around the reactor vessel by defining an inter-vessel space (E) with the reactor vessel; - a tank (10), called the drain tank, arranged below the vessels, and connected to the inter-vessel space by at least one pipe (11) and to the outlet of the reactor vessel by at least one pipe (12); - a selective closure device (13) for the outlet of the reactor vessel, in the closed position during normal reactor operation and in the open position to carry out the emptying of the reactor vessel.Figure for the abridged version: fig.3.

The invention provides a neutron-gamma dual-mode detection method based on a 6Li-containing scintillator. The neutron-gamma dual-mode detection method solves the defect that a current neutron-gamma dual-mode detector with preset screening parameters has limitation in scenes with severe environmental changes such as reactor monitoring and petroleum logging. According to the invention, the unsupervised learning PCA-GA-K-means algorithm is configured to carry out label-free training in the upper computer of the detection system, and the trained model is transmitted to the FPGA to carry out waveform processing, so that the accuracy and efficiency of the FPGA for classifying neutron and gamma signals are improved. Meanwhile, the detection system extracts statistical decay time of neutrons and gamma waveforms to serve as reference quantity of environmental fluctuation, clustering algorithm parameters can be optimized in time when waveform difference remarkably changes, environmental compatibility of the detection system is remarkably improved compared with a traditional method, and operation complexity and cost of the detection system are reduced.

The embodiment of the invention provides a synchronous coupling analysis method and device for reactor thermal software, and belongs to the technical field of nuclear power. The method comprises the following steps: stepping a first time point by a first point reactor time step length to obtain a second time point of the point reactor neutron dynamics model; matching the second time point with a third time point of the thermal hydraulic model under the condition that a point reactor calculation result of the point reactor neutron kinetic model at the second time point meets a preset calculation precision requirement to obtain a matching result; and under the condition that the matching result indicates that the second time point is not matched with the third time point, adjusting the first point heap time step length, updating the second time point to the first time point, and skipping to the step of stepping the first time point by the first point heap time step length for execution. And until the matching result indicates that the second time point is matched with the third time point. According to the embodiment of the invention, time synchronization of the two models can be realized.

The invention relates to a nuclear power plant comprising: - a reactor building (10); - at least two reactor pits implanted inside the reactor building, - at least two reactor vessels (2) of molten salt fast neutron nuclear reactors (1), the reactor vessels exhibiting axial symmetry about a central axis, internally delimiting a primary circuit for a fuel in liquid form in which at least one salt is melted, the interior of the vessel being devoid of moderator material; each of the reactor vessels being housed in one of the two reactor pits; and - means for transferring the molten salt fuel from inside one of the two reactor vessels into the other of the two reactor vessels.

The invention relates to a single event effect sensitivity detection method and device, equipment and a storage medium. The method comprises the following steps: acquiring a to-be-analyzed area of a to-be-detected sample; emitting a primary ion beam to the to-be-analyzed area through a secondary ion mass spectrometer; the primary ion beam is used for exciting an area to be analyzed to generate secondary ions; determining the target signal intensity of the to-be-analyzed area according to the mass-to-charge ratio and the signal intensity of the secondary ions received by the secondary ion mass spectrometer; and under the condition that the boron-10 isotope content corresponding to the target signal intensity is higher than a preset threshold value, determining that the to-be-detected sample is sensitive to the thermal neutron single event effect. By adopting the method, the detection cost can be reduced while the detection accuracy is ensured.