14 results about "Neutron measurement" patented technology

The invention provides a joint optimization method for a stacking sequence and a grabbing posture of a neutron measurement system, and relates to the field of data processing. According to the method, multi-source monitoring data of a neutron measurement system are collected, shadow voxels are constructed in combination with a three-dimensional space model, a neutron resonance shadow domain is formed through clustering superposition, and a dangerous concentration cloud cluster and a safe rarefied area are marked; mapping candidate stacking positions and postures according to sample mass distribution, geometric dimensions, centroid positions and irradiation sensitive characteristics, generating a stacking mode and determining a stacking sequence; performing path risk assessment on the grabbing postures, and selecting the grabbing postures of which the crossing risk meets a threshold value; superposing micro-random jitter on the path to suppress resonance phase locking; and abnormal events are monitored in real time during operation, and a risk domain is updated to execute hierarchical unloading control, so that the instantaneous impact and damage risk is reduced. According to the technical scheme, the probability of instantaneous impact risks caused by stacking overall micro-drift and grabbing track overlapping can be effectively reduced, and therefore the safety of the system is guaranteed.

The invention provides a joint space smooth motion trail generation method of a multi-ball neutron spectrometer ball changing device, and relates to the field of data processing. According to the method, a topological framework is constructed by extracting key static postures of a ball changing process, and a plurality of operation fibers are sampled and verified in a joint space channel to form a weaving domain; acquiring short-time sequence characteristics such as irradiation temperature, sphere temperature rise, contact force and structural vibration in real time, and compressing the short-time sequence characteristics into thermal disturbance fingerprints; screening target operation fibers meeting safety margin and vibration constraint according to the mapping relation, and dynamically modulating the weights of the operation fibers through thermal disturbance fingerprints; and dividing a micro-cycle weaving window to limit a weight change rate in combination with a neutron measurement rhythm, and realizing smooth and safe trajectory output under thermal deformation interference. By implementing the technical scheme provided by the invention, the safety of the ball changing device of the multi-ball neutron spectrometer in the ball changing process is 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 present application relates to the technical field of data processing and remote maintenance of oil logging instrument, and particularly relates to a remote data calibration method and system for a neutron measurement system. The method comprises the following steps: collecting multi-dimensional time sequence data of downhole instrument, and identifying the current temperature change state; based on the principle of non-steady-state heat conduction, the thermal hysteresis index is calculated by using the temperature change rate and the material thermal saturation limit constant; the real temperature of the crystal is reconstructed by using the thermal hysteresis index to inversely correct the measured temperature of the sensor; and based on the equivalent lattice temperature, the original energy spectrum characteristics are dynamically gain calibrated by using a preset quadratic polynomial multiplication compensation model. By reconstructing the real temperature of the crystal, the present application eliminates the gain hysteresis loop in the up-measuring and down-measuring processes, and significantly improves the interpretation accuracy and consistency of the logging data in a complex variable temperature environment.

The invention relates to the technical field of data processing and remote maintenance of petroleum logging instruments, in particular to a remote data calibration method and system for a neutron measurement system. The method comprises the following steps: collecting multi-dimensional time sequence data of an underground instrument, and identifying a current temperature change state; calculating a thermal hysteresis index by using a temperature change rate and a material thermal saturation limit constant based on an unsteady state heat conduction principle; performing reverse correction on the actually measured temperature of the sensor by using the thermal hysteresis index, and reconstructing the equivalent lattice temperature in the crystal; and based on the equivalent lattice temperature, performing dynamic gain calibration on the original energy spectrum characteristics by using a preset quadratic polynomial multiplication compensation model. According to the invention, by reconstructing the real temperature of the crystal, a gain lag loop in the upper measurement and lower measurement processes is eliminated, and the interpretation precision and consistency of logging data in a complex variable-temperature environment are remarkably improved.

The application discloses a kind of metal halogen perovskite-based neutron multiplicity measuring device and method, the device includes: shell, the shell is used to install and protect other components of the measuring device;Radiation detection module is arranged in the shell, and the radiation detection module is mainly composed of perovskite material and photomultiplier tube etc.;Shielding unit is arranged in the shell and located at the side and bottom of the perovskite scintillator, for reducing gamma-ray background;And, readout electronics module is arranged in the shell, and the readout electronics module is used to read the electrical signal generated by the photomultiplier tube and convert it into digital signal output.The application can realize the effective discrimination of neutron and gamma, so as to accurately deduct the influence of gamma-ray background, improve the sensitivity of fast neutron measurement.

A method for determining the quantity of plutonium in a radioactive sample in the presence of curium, comprising the steps of: Measuring (301) a train of electrical pulses using a radiation detection system, Determining (302), respectively in a first and a second time window, a first and a second number of second-order pulse coincidences between the electrical pulses supplied by the detectors, The second time window being formed by the union of the first time window and a third time window, The first and third time windows being chosen such that the number of second-order pulse coincidences related to plutonium is greater than that related to curium in one of the two windows between the first and third time windows and less than that related to curium in the other window,Determine (304) the quantity of plutonium by applying a nonlinear regression model taking as parameters: the total number of measured pulses, the first number of second-order pulse coincidences, and the second number of second-order pulse coincidences, the model having been previously trained on a set of values ​​simulated from a numerical model. Figure 3,

The present invention relates to a method for installing a temporary neutron measurement system (TNMS) mounted on a core of an integrated nuclear reactor, comprising the steps of: (S10) arranging, inside a reactor core, a measurement assembly capable of measuring neutrons discharged from the reactor core; and (S20) connecting, to the measurement assembly, a connection assembly for supplying power to the measurement assembly and receiving a measurement signal.

The application provides a GM counting tube suitable for alpha / beta / gamma ray and neutron measurement and a manufacturing method thereof. The GM counting tube comprises a cathode shell, a first detection window and a second detection window, a boron neutron sensitive layer coated on a part of the outer surface of the first detection window and / or a part of the outer surface of the second detection window, an insulating seat, a first anode wire and a second anode wire with a hole in the middle, wherein the first end of the second anode wire is communicated with the middle part of the first anode wire, and the second end of the second anode wire penetrates through the insulating seat and is led out to the outside of the cathode shell. The GM counting tube realizes the function of simultaneously detecting alpha, beta, gamma ray and neutron, and the boron neutron sensitive layer is on the outer surface of the detection window, so that daily maintenance and repair are facilitated.

The application discloses a digital visualized reactivity measurement method, device, system and equipment, and the method comprises the following steps: obtaining a digital neutron measurement signal by using a front-end digitization-based signal measurement method; establishing a three-dimensional physical analysis model by using a three-dimensional digital coordinate positioning-based digital modeling method; correcting the three-dimensional physical analysis model by using a three-dimensional calculation model optimization method based on a measured critical rod position to obtain a corrected calculation model; obtaining a correction factor based on the corrected calculation model, correcting the digital neutron measurement signal to obtain a corrected neutron detection signal; performing reactivity measurement based on the corrected neutron detection signal; and establishing a three-dimensional core visualized model based on the corrected calculation model, and displaying the reactivity measurement result in a numerical form on the three-dimensional core visualized model. The application realizes accurate and reliable digital visualized reactivity measurement, and provides a theoretical basis for efficient and accurate measurement of core reactivity physical parameters.

A nuclear reactor neutron measurement channel mounting device, including a column, ring seat, positioning cylinder, rotating mounting part, rotating mounting part is connected with the column, both closely fit; rotating mounting part and ring seat are positioned and installed through positioning cylinder; The column is equipped with fixed shell, column rib, and the column rib is fixed on the shell; The upper silver linear guide linear slide rail A and the upper silver linear guide linear slide rail B are fixed on the shell with bolts; The handle is connected on the left and right sides of the shell; The screw rod seat A and the screw rod seat B are bolted on the upper surface of the shell; The screw rod carries the supporting plate, and the tension and pressure sensor is installed on the supporting plate, and is fixed through the tension and pressure sensor mounting plate; The supporting plate is in contact with the sliding supporting plate, and the inclined pull rib connects the sliding plate and the clamping jaw part; The column bottom plate is fixedly connected with the fixed shell and the column rib, and a circular groove is formed in the middle of the column bottom plate for cooperation with the positioning cylinder; The upper column cover is bolted with the top supporting part.

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.

The application provides a sampling measurement width calculation method of a radial collimator, a terminal and a storage medium. The sampling measurement width calculation method comprises the following steps: S101: setting a sample diameter and a neutron slit width according to a sampling measurement width theoretical value, and selecting a step distance through the sampling measurement width theoretical value and the sample diameter; S102: obtaining a neutron intensity distribution experimental curve through scattered neutron measurement based on the step distance, and obtaining a sampling measurement width value according to the neutron intensity distribution experimental curve and the sample diameter. The application can obtain an accurate sampling measurement width value, is not prone to calculation deviation, and improves the accuracy and reliability of a measurement result.

This invention discloses a plutonium-containing material measuring device, relating to the technical field of radioactive element measuring devices. The device includes a measuring chamber, a lower cover assembly, and an automatic feeding structure. A gamma detector is installed above the measuring chamber, and a neutron detector is installed inside. The automatic feeding structure includes a horizontal transmission mechanism and a synchronous lifting mechanism. The synchronous lifting mechanism is a symmetrical structure driven by a single power source. The lower cover assembly, which carries the material to be measured, is placed on the horizontal transmission mechanism and can be conveyed horizontally to the lifting position. The synchronous lifting mechanism then conveys the lower cover assembly along with the material to be measured vertically into the upper measuring chamber, and the lower cover assembly seals the bottom of the measuring chamber, thus forming a closed measuring space. The device provided by this invention can simultaneously perform neutron and gamma measurements on materials, reducing measurement time, minimizing transport time, reducing radiation hazards to personnel, reducing equipment size, and increasing measurement accuracy.