27 results about "Neutron count" patented technology

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 invention belongs to the technical field of nuclear material measurement and analysis, and particularly relates to a neutron detection method for measuring the mass of a nuclear material and a radiation dose field of the nuclear material. According to the embodiment of the invention, the method comprises the steps: carrying out the energy response calculation and calibration of a detector through a parallel beam standard neutron source, and obtaining a calibration factor; performing energy response calculation and calibration on the detector by taking a to-be-measured object as a target object, determining the energy response and fluence-ambient dose equivalent conversion coefficient of the detector in a radiation field of the to-be-measured object, and realizing simultaneous measurement of a neutron counting rate, a fluence rate and an ambient dose equivalent rate; and the requirements of carrying out radiation dose field monitoring while carrying out quantitative analysis on the to-be-detected object in a special scene are met. The technical scheme of the invention can be popularized and applied to fixed-point monitoring of a to-be-detected system with known or measurable nuclear material source item composition and isotope abundance in nuclear facilities, or retention volume analysis and radiation dose measurement before transfer or treatment of some equipment for treating nuclear materials.

This invention relates to a welding temperature gradient control method and apparatus based on neutron source residual stress detection, belonging to the field of welding control technology. This technology establishes a correlation between laser power, beam size, scanning rate, metal type, and temperature by constructing a temperature field data acquisition module and a heating and cooling module for the welding process, and by using laser-assisted local heating and forced substrate cooling devices. It develops a temperature gradient control method to achieve online physical simulation of the temperature gradient between the welding zone and the substrate, solving the problem of mismatch between the welding cooling rate and the neutron data acquisition rate, and realizing in-situ online testing of the stress field near welding conditions.

The embodiment of the application provides a kind of neutron flux abnormality detection method and device, electronic equipment and storage medium, belong to nuclear power plant safety technical field.The method comprises: screening reference nuclear power reaction unit.Get the first reference counting rate detection module in multiple continuous preset time steps under the core neutron counting rate.Acquire concentration influence factor, original neutron source source intensity and reference neutron source source intensity.According to the first detection sensitivity, the first reference sensitivity, the core neutron counting rate, the concentration influence factor, the original neutron source source intensity and the reference neutron source source intensity, the predicted neutron flux of the core basket is obtained by calculation.The first loading of pressurized water reactor nuclear power reaction unit is carried out, and the target neutron counting rate is obtained.According to the target neutron counting rate and the first detection sensitivity, the target neutron flux is obtained by calculation, and the abnormality is detected based on the target neutron flux and the predicted neutron flux.The embodiment of the application can improve the efficiency of neutron flux abnormality detection.

The invention relates to a directional neutron energy spectrum measuring device which is characterized in that a moderation box body is internally provided with moderation liquid and is provided with an upward opening end, a neutron beam is emitted perpendicular to any box body side wall of the moderation box body, and the moderation box body is used for moderating the neutron beam; the thermal neutron detection system is placed in the moderation box body and is used for detecting neutron counts corresponding to the neutron beams at a plurality of positions in the moderation box body to obtain a neutron energy spectrum; and the moving assembly is connected with the thermal neutron detection system, is mounted at the opening end of the moderation box body, and is used for driving the thermal neutron detection system to move in the moderation box body in multiple directions. The purpose of driving the thermal neutron detection system to move in the moderation liquid of the moderation box body through the moving assembly is achieved, and therefore the technical effects that one thermal neutron detection system can move in the moderation liquid, a moderation ball does not need to be replaced, operation is easy, and the risk that employees are irradiated is reduced are achieved.

The invention discloses a two-parameter detector and a two-parameter real-time detection method and system for BNCT, and the detector comprises a sensing element which is made based on a Li2B4O7 crystal; the signal acquisition module is configured to respectively acquire an electric pulse signal and an electric parameter signal for indicating neutron counting from the sensing element; the signal conversion module is used for converting an electric pulse signal for indicating neutron counting into effective pulse counting and converting the electric parameter signal into a resistance parameter; the model calculation module is used for carrying a two-parameter response model and carrying out data processing on the resistance parameters based on the model to obtain corrected neutron flux; the technical problems that in the BNCT treatment process, a gamma-ray energy spectrum analysis method adopted in the prior art is likely to cause interference on the measurement result of the boron concentration, and real-time and rapid monitoring of the boron concentration is difficult to achieve are solved.

The invention provides a quality measurement method, a model training method, electronic equipment, a storage medium and a program product. The method comprises: obtaining neutron counting data of a nuclear material to be measured within a first measurement duration, the first measurement duration being less than a second measurement duration, and the second measurement duration being a duration for performing neutron multiplex measurement on the nuclear material to be measured based on a preset mathematical model; based on the neutron counting data, a neural network model is used for conducting mass measurement on the to-be-measured nuclear material, a measurement result output by the neural network model is obtained, and the measurement result represents the mass of the to-be-measured nuclear material. By means of the scheme, the accuracy of nuclear material quality measurement can be improved under the condition that the measurement time of the to-be-measured nuclear material is shortened.

The application discloses a porosity calculation method and system for complex reservoirs, which comprises the following steps: selecting a marker layer, and performing preliminary correction on original neutron and density logging curves of a target layer by using deviation analysis according to skeleton neutron values and skeleton density values of the marker layer; based on core analysis test data of the target layer, core data is homed in the preliminary corrected neutron and density logging curves, and a fusion analysis chart is formed based on this; the fusion analysis chart is corrected in neutron values by using a neutron multiplication factor initial value, and a neutron multiplication factor final value is determined by comparing a formation porosity calculation value obtained by using the corrected neutron and density with a formation porosity measurement value; and the original neutron and density logging curves are comprehensively corrected by using the preliminary correction amount and the neutron multiplication factor final value, so that the formation porosity of a single well is obtained.

The present application relates to the technical field of neutron logging, and particularly relates to a neutron logging method, system and electronic equipment for measuring formation porosity, the method comprising: when a target formation of a well to be measured is a high-porosity formation, substituting a thermal neutron count ratio of the target formation and formation density of the target formation into a high-formation porosity model to obtain formation porosity of the target formation; when the target formation of the well to be measured is a low-porosity formation, substituting the thermal neutron count ratio of the target formation and the formation density of the target formation into a low-formation porosity model to obtain formation porosity of the target formation. Compared with the prior art, the present application starts from neutron transport theory, fully considers the influence of non-elastic scattering of neutrons on neutron moderation, and finally improves the accuracy and sensitivity of porosity measurement of the target formation. Moreover, the instruments used in the method are common instruments and equipment in the field, which are convenient to operate, implement and test.

The invention provides a device and a method for measuring the surface density of a neutron absorbing material B10. The device comprises a control system, a driver, a neutron detector and a sample holder. The sample rack is used for slidably arranging a to-be-tested sample and a standard sample; the neutron detector is arranged on the sample rack and is used for measuring and outputting neutron data after a neutron beam passes through the to-be-measured sample or the standard sample; the control system is used for receiving measurement data of the neutron detector, calculating the B10 surface density of the to-be-measured sample and controlling the measurement position of the to-be-measured sample and / or the standard sample on the sample rack; the driver is respectively connected with the control system and the sample rack, and drives the to-be-tested sample and / or the standard sample to horizontally move and / or vertically move on the sample rack based on an instruction of the control system. According to the invention, the measurement position of the neutron absorption material can be accurately controlled, accurate measurement of the B10 surface density is realized by using the standard sample with the same raw material and processing technology as the to-be-measured sample, and the neutron absorption performance of the neutron absorption material is accurately evaluated.

The invention relates to the field of neutron energy spectrum detection methods, in particular to a rotating hemisphere neutron energy spectrum detection device and method based on a liquid moderator, and the device comprises a liquid pumping and injecting device, a center detector, a plurality of mutually independent moderation cavities, a rotating hemisphere concentric spherical shell and a rotating device. The method comprises the following steps: simulating characteristic peak response or neutron response under different thickness moderator combinations by utilizing a Monte Carlo method, and compiling the characteristic peak response or neutron response into a corresponding response function matrix; a center detector is used for measuring characteristic gamma ray counts or thermal neutron counts under different thickness moderator combinations to form a count value matrix; and solving by combining the response function matrix and the measured count value matrix to obtain the neutron energy spectrum of the to-be-measured region. According to the invention, the filled moderator combination is directly rotated, and the water pumping and injection time is saved compared with a water pumping and injection type single-sphere neutron energy spectrometer.

A method for measuring porosity of a subterranean formation includes the steps of: positioning a nuclear logging tool having one or more neutron sources and two or more dual function detectors in a subterranean formation; causing the one or more neutron sources to emit neutrons in a plurality of neutron pulses toward the subterranean formation and to generate neutrons and gamma rays in the subterranean formation; obtaining one or more neutron count rates for each of the two or more detectors; determining a formation type of the subterranean formation based on the gamma rays received by the one or more detectors; calculating one or more neutron count rate ratios between the neutron count rates of two detectors selected from the two or more detectors; and obtaining one or more formation porosities based on the formation type and the one or more neutron count rate ratios.

The application discloses a formation density measurement method, a storage medium and equipment, and relates to the field of well logging technology. The method comprises the following steps: establishing a neutron logging model of formation density for representing the relationship between the formation density and the non-elastic gamma count ratio and the thermal neutron count ratio; and substituting the non-elastic scattering gamma ray count ratio, the thermal neutron count ratio and a plurality of calibration coefficients of a target formation of a well to be measured into the neutron logging model of formation density to obtain the formation density of the target formation of the well to be measured. According to the method, the final formation density can be obtained by using the thermal neutron and the non-elastic gamma count. The method has the characteristics of small influence of formation lithology, high measurement efficiency and simple design of related instruments.

The invention discloses a water injection multi-sphere neutron energy spectrum measurement device and method, and belongs to the technical field of neutron energy spectrum measurement, the device is characterized in that a plurality of concentrically nested spherical shells are connected to the same supporting cylinder, a through channel is arranged in the center of the supporting cylinder, and a through flow channel is arranged in the column wall; the through flow channel is respectively communicated with each inter-shell cavity, is provided with a one-way valve, and is also provided with an air pipe and an overflow hole; water is sequentially injected into the cavity between the shells through the water channel, neutron counts under different water layers are obtained through the neutron detector, and then the energy spectrum of the neutrons to be measured is obtained through calculation; by means of the mechanical one-way valve and the water flow channel of a special structure, water can be injected into air between the shells from inside to outside in sequence, water can be drained at the same time through gravity, compared with an electromagnetic valve, the device is more stable and durable, an external cable is not needed, the service life of the whole device is greatly prolonged, and the machining and manufacturing difficulty of the device is reduced.

The present application relates to a kind of plutonium-containing material quality analysis method, by the following steps: the calculation model of measurement object is established, the detection efficiency when loading different material amount is simulated by MCNP, the detection efficiency library of material spontaneous fission neutron under the calculation model is calculated;The detection efficiency of neutron counting module corresponding to different C value is calculated and verified, and the detection efficiency ε of corresponding neutron counting module is judged according to the C value when loading material;The total number of neutrons S of neutron counting module, the detection efficiency ε of neutron counting module is used to calculate the material quality m loaded in mixing funnel.The method provided by the present application can be used to quickly monitor the material content in mixing funnel using neutron analysis method under the condition that the process is basically stable, obtain the material content in mixing funnel, to realize real-time measurement of material quantity under special conditions, and the measurement deviation is less than 10%, meet the normal operation and safety requirement of process production, can realize normal filling and transfer storage of material.

This invention provides a uranium content detection method, device, storage medium, and electronic device, belonging to the field of mineral exploration technology. The uranium content detection method includes: acquiring well logging data, which includes hyperthermal neutron counts, thermal neutron counts, and macroscopic scattering cross-section information, obtained by logging after emitting pulsed neutrons into the well to be logged; calculating the formation uranium content based on the hyperthermal neutron counts, thermal neutron counts, and macroscopic scattering cross-section information using a pre-set formation uranium content calculation model, which is based on a numerical simulation model of uranium content, mineralization, and porosity conditions established using the Monte Carlo method. This method can eliminate the errors caused by formation porosity and mineralization in the uranium content calculation process, improving the accuracy of formation uranium content evaluation and the efficiency of uranium ore detection.

The application provides a method and a device for monitoring subcriticality in a reactor physics startup process, which can be applied to the field of reactor physics technology. The method comprises the following steps: obtaining neutron count change data of a reactor in a physics startup process; processing the neutron count change data based on an inverse kinetics method to obtain a first criticality; processing the neutron count change data based on an extrapolation method to obtain a second criticality; and determining the subcriticality of the reactor according to the first criticality and the second criticality. Embodiments of the application can calculate the subcriticality of the reactor in the physics startup process by combining the inverse kinetics method and the extrapolation method through neutron count change data. By combining the inverse kinetics method and the extrapolation method, the subcriticality of the reactor can be more accurately measured.

The embodiment of the invention provides a neutron fluence rate anomaly detection method and device, electronic equipment and a storage medium, and belongs to the technical field of nuclear power station safety. The method comprises the following steps: screening out a reference nuclear power reaction unit; and obtaining the reactor core neutron counting rate of the first reference counting rate detection module in a plurality of continuous preset time steps. And acquiring a concentration influence factor, an original neutron source intensity and a reference neutron source intensity. And performing calculation according to the first detection sensitivity, the first reference sensitivity, the reactor core neutron counting rate, the concentration influence factor, the original neutron source intensity and the reference neutron source intensity to obtain a predicted neutron fluence rate of the reactor core hanging basket. Charging the pressurized water reactor nuclear power reaction unit for the first time, and obtaining a target neutron counting rate; and performing calculation according to the target neutron counting rate and the first detection sensitivity to obtain a target neutron fluence rate, and performing anomaly detection based on the target neutron fluence rate and the predicted neutron fluence rate. According to the embodiment of the invention, the efficiency of neutron fluence rate anomaly detection can be improved.

This technology provides a way to measure the moisture content and water content of fuel debris storage containers. [Solution] The measurement system comprises a neutron generator that irradiates the object to be measured with neutrons, a neutron detector that detects neutrons in different energy bands, and a measuring device that generates a neutron spectrum based on the neutron count rate detected by the neutron detector and measures the amount of water and / or hydrogen in the object to be measured based on the spectral information of the medium velocity group and above in the neutron spectrum.

This application discloses a material testing method, apparatus, equipment, medium, and product. The material testing method includes: controlling a target neutron source to emit raw neutron beams into moderators of various thicknesses, so that the raw neutron beams are moderated by the moderators of different thicknesses, generating multiple neutron beams; obtaining the number of non-thermal neutrons and the total number of neutrons in the neutron beams; determining the number of thermal neutrons and the proportion of thermal neutrons corresponding to each neutron beam based on the number of non-thermal neutrons and the total number of neutrons; identifying the neutron beam with the highest number of thermal neutrons and the highest proportion of thermal neutrons from the multiple neutron beams as the target neutron beam, and determining the thickness of the moderator corresponding to the target neutron beam as the target thickness; performing a thermal neutron shielding test on the target material based on the target moderater of the target thickness to obtain the thermal neutron shielding rate corresponding to the target material. According to the embodiments of this application, the accuracy of the thermal neutron shielding rate test results for materials can be improved.

The utility model provides a reactor structure for realizing a starting-free neutron source in subsequent circulation, which comprises a reactor body and a signal amplification device, and the signal amplification device is of a cavity shell structure and is arranged between a fuel assembly in the reactor and a neutron detector outside the reactor. And the neutron detector is located on a neutron radiation path between the fuel assembly and the neutron detector. According to the utility model, by utilizing the arranged signal amplification device, the thickness of a shielding water layer between the spent fuel assembly and the reactor external source range neutron detector is reduced during the subsequent circulating reactor core loading period, and the number of neutrons reaching the detector is increased, so that the reactor core can be loaded with the spent fuel assembly which does not reach the minimum burnup. The detector can obtain effective counting in the loading process without depending on a neutron source, so that the problem that the neutron fluence rate level in a reactor core is difficult to accurately measure by the out-of-core neutron detector under the condition that the signal-to-noise ratio is large enough is solved.

The invention provides a correction method, device, model and system for neutron porosity logging while drilling. According to the while-drilling controllable source porosity logging instrument model, performing simulation analysis on the near-far thermal neutron counting ratio response under different environmental parameters to obtain a simulated neutron data set; according to the simulated neutron data set, performing fitting processing on the real porosity of the stratum to obtain an apparent porosity calculation formula; according to an apparent porosity calculation formula, processing the target environment parameters, and generating a discrete correction value formula for describing a corresponding relationship between the porosity correction value and the apparent porosity under each target environment parameter value; and completing continuous correction of the while-drilling neutron porosity logging based on the correction value formula and the target environment parameters. The discrete influence of environmental factors is converted into a continuous function, dynamic correction under the complex borehole condition is completed, and an efficient and high-precision solution is provided for neutron porosity logging under the complex borehole condition.

The invention relates to a nuclear reactor control rod calculus value measuring method and device. The method comprises the following steps: when a nuclear reactor is in a preset state, controlling a control rod of the nuclear reactor to move based on a preset rod position, and acquiring a neutron data sequence of the nuclear reactor for each section of rod position of the control rod, and determining a control rod differential value corresponding to each section of rod position of the control rod according to the neutron data sequence, multiplying the control rod differential value corresponding to each rod position by a step number, and summing to obtain a control rod integral value of the control rod. By adopting the method, the universality of the measurement method for the control rod calculus value can be improved.

This invention discloses a direct measurement system and calibration method for neutron microphysical parameters in rock cores under experimental conditions, belonging to the field of neutron measurement technology in petroleum exploration. The system includes: establishing a space-field reference, sample transmission measurement, geometric boundary effect correction, physical parameter inversion, and equivalent parameter conversion. Addressing the significant boundary effects in the laboratory, this invention constructs a high signal-to-noise ratio neutron transmission detection system, employing digital pulse waveform discrimination technology to effectively eliminate gamma-ray interference within a microsecond-level time window, achieving pure neutron count extraction. A dual correction calibration algorithm of "geometric factor-mass attenuation" is proposed, converting the finite-volume core count rate into standardized neutron parameters equivalent to well logging data. This method fills a gap in the field of experimental neutron measurement in rock physics, providing reliable experimental data support for lithological identification of complex reservoirs such as deep carbonate rocks and for the correction of well logging interpretation models.

Device which is configured to hold a nuclear fuel and has one or more neutron sources which are configured to emit free neutrons which can interact with isotopes of the nuclear fuel, wherein the one or more neutron sources are configured such that the neutron flux strength of the generated neutrons is more than 10 12 neutrons per second and the one or more neutron sources have a power supply by means of which the neutron flux strength can be controlled.

The invention discloses a reservoir fluid identification method and device, electronic equipment and a medium, and is applied to the field of sandstone reservoirs. The method comprises the following steps: acquiring original conventional data and reservoir density of a reservoir corresponding to a to-be-measured well log, and determining an original curve corresponding to the original conventional data; performing correction processing on the original curve based on the correction curve specification to obtain a corrected curve; determining a neutron-sound wave envelope area formed by neutron data and sound wave data in the original conventional data according to the corrected curve; and based on a reservoir fluid identification judgment criterion, determining a fluid type corresponding to the reservoir according to the reservoir density and the neutron-sound wave envelope area. According to the method, the type of the reservoir fluid is judged by comprehensively analyzing the two parameters of the neutron-sound wave envelope area and the reservoir density, the parameters are not influenced by factors such as formation resistivity and human factors, the properties of the reservoir fluid can be accurately, rapidly and visually judged, and the judgment accuracy of the reservoir fluid is improved.

The application relates to a neutron source azimuth measurement device and method. The method comprises a neutron source to be measured, a polyhedral neutron detector, a neutron moderator structure and an electronic and data acquisition system; the neutron moderator structure is wrapped outside the polyhedral neutron detector; the polyhedral neutron detector is connected by a plurality of planar neutron detectors, each planar neutron detector is connected with the electronic and data acquisition system; the electronic and data acquisition system comprises a ratio calculation module and an azimuth acquisition module; the ratio calculation module obtains a neutron count rate according to the number of electric pulse signals output by the planar neutron detector per unit time, and obtains a relative ratio of the neutron count rate between each planar neutron detector, and the azimuth acquisition module is used for inputting the relative ratio into a pre-trained azimuth acquisition model to obtain the azimuth of the neutron source to be measured. The method can shorten the neutron source azimuth measurement time and improve the neutron source azimuth measurement precision.