201 results about "Neutron detection" patented technology

The embodiment of the invention provides an anomaly identification method and device for an out-of-core neutron detector, electronic equipment and a medium, and belongs to the technical field of nuclear power. The method comprises the following steps: acquiring a plurality of original currents measured by a plurality of out-of-core neutron detectors at a first moment; correcting each original current by using the correction coefficient of the quadrant corresponding to the original current to obtain a corrected current; according to the correction current set of each section, a deviation monitoring parameter value of each section is obtained through calculation; if the deviation monitoring parameter value corresponding to the target cross section is greater than or equal to the target threshold value of the target cross section, determining that the reactor core or the out-of-core neutron detector is abnormal at the target cross section; judging whether the reactor core is abnormal at the target section or not through a reactor core power distribution measurement mode; and if the reactor core is not abnormal at the target section, determining that the out-of-core neutron detector is abnormal at the target section. According to the embodiment of the invention, the abnormal position of the out-of-pile neutron detector can be accurately positioned.

The invention discloses a sensor error compensation method based on a thermal expansion effect deformation model, and aims to solve the problem of measurement error increase caused by thermal expansion and cold contraction of a sensor in a high-temperature environment. The method comprises the following steps: firstly, carrying out multi-material thermal expansion parameter acquisition and modeling, and constructing a composite sensor structure and geometric parameters; secondly, designing a static compensation algorithm by using output calibration data of the sensor at different temperatures, and correcting output errors caused by the temperatures; finally, dynamic compensation and a self-adaptive correction mechanism are introduced in the actual operation process, and residual errors are corrected in real time. The method is suitable for a multi-sensitive-element composite sensor structure comprising a self-powered neutron detector and other auxiliary sensing elements, and the measurement precision and stability of the sensor under the high-temperature condition are improved in a mode of combining static calibration and dynamic compensation.

The invention provides a high-integration-level signal reading module for a neutron proportional counter tube, and belongs to the technical field of neutron detection, the high-integration-level signal reading module comprises stacked double-layer circuit boards, and the upper circuit board and the lower circuit board are connected through pin interfaces; the upper circuit board is provided with a signal processing circuit which is used for reading, amplifying, discriminating and shaping signals of the neutron proportional counter tube. The lower-layer circuit board is provided with a positive and negative dual-power-supply support circuit which provides + / -3.3 V power supply support for the signal processing circuit of the upper-layer circuit board. The module supplies power through the lower-layer power panel, and the lower-layer circuit board supplies positive and negative power to the upper-layer circuit board after completing power conversion. Signals are input through the IPX interface of the upper-layer circuit board and are output through the other IPX interface after being processed. The charge sensitive pre-amplifier, the broadband voltage amplifier, the pulse discriminator circuit, the pulse shaping circuit and the power management module are integrated in the same module, so that the real integrated design is realized.

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

The invention discloses a neutron energy spectrum analysis method and device based on energy response and a medium, and relates to the technical field of neutron energy spectrum analysis, and the method comprises the steps: carrying out the particle transportation simulation of a neutron detector, and constructing a two-dimensional response matrix of a neutron injection energy interval and a detector output channel; carrying out discretization, fitting and energy segment compression on the response matrix to obtain an energy response matrix for spectrum inversion; sampling, shaping and normalizing an output signal of the detector, and constructing a measurement spectrum; the neutron energy spectrum is solved and evaluated by improving a spectrum inversion algorithm and combining multi-source spectrum parallel initialization and an adaptive step size structure. According to the invention, accurate characterization of the response characteristics of the detector is realized, the resolution and stability of spectrum inversion are improved, error accumulation and overfitting are inhibited, and the accuracy and reliability of neutron spectrum analysis are enhanced.

The invention provides a mountain freeze-thaw desertification early warning method and related equipment. The method comprises the following steps: acquiring thermal neutron intensity and epithermal neutron intensity of a target area; based on a target intensity ratio and a pre-obtained empirical fitting parameter set, target parameters are determined, and the target intensity ratio is the ratio of the thermal neutron intensity to the epithermal neutron intensity of the target area; determining a target moisture content according to the target parameter and the thermal neutron intensity or epithermal neutron intensity of the target area; and when the target moisture content is lower than a preset critical soil moisture threshold value, carrying out mountain freeze-thaw desertification early warning. Soil moisture is inverted through a cosmic ray neutron detection technology, environmental interference factors such as a non-soil water hydrogen source are corrected, local soil moisture of different vegetation types and soil types is accurately captured, freeze-thaw desertification is judged in combination with a critical soil moisture threshold, and early warning is given.

The invention discloses a high-detection-efficiency groove silicon carbide neutron detector structure, and relates to the technical field of semiconductor neutron detection, a plurality of groove groups are etched on the top surface of a SiC substrate, and each groove group comprises groove units which are sequentially connected along the direction of a first central plane of the SiC substrate; each groove unit comprises a first groove and a second groove which are symmetrically arranged, and the bottom faces of the first grooves and the bottom faces of the second grooves are parallelograms which are symmetrically arranged. According to the neutron detector, the groove structure of a traditional neutron detector is improved, the filling area of the neutron conversion material is increased due to the arrangement of the through groove groups, meanwhile, the contact area of the neutron conversion material and the SiC region is also increased, the self-absorption effect of secondary particles is reduced, and the detection efficiency of the detector is remarkably improved.

The invention relates to the technical field of data calibration, in particular to a neutron fluence response calibration method based on a neutron generator reference radiation field, and the method comprises the steps: collecting a counting rate and a neutron fluence rate at each moment in each monitoring period through a neutron detector and a neutron generator; data of each environmental parameter around the reference radiation field at each moment in each monitoring period are obtained; recording each monitoring period and a plurality of monitoring periods before the monitoring period as historical periods; determining the measurement error of each historical period; obtaining the measurement interference degree of each environmental parameter in each monitoring period; and calculating the scattering interference degree of each environmental parameter in each monitoring period to obtain a calibration counting rate, and carrying out real-time calibration on the neutron fluence response. According to the invention, the interference influence of different environmental factors on the measurement result of the neutron detector can be quantified through dynamic environmental changes, the measurement result of the neutron detector is calibrated in real time, and the measurement accuracy of neutron fluence response is improved.

The invention belongs to the technical field of nuclear logging data processing, and particularly relates to a neutron detector pulse signal intelligent discrimination method and system based on deep learning, and the method comprises the following steps: collecting a pulse signal outputted by a detector, and when the rising edge of the pulse signal is detected to exceed a preset ground noise threshold value, determining the pulse signal; intercepting a time sequence containing the complete pulse signal, and carrying out normalization processing on the time sequence to obtain a normalized dimensionless voltage sequence; and calculating a first-order difference absolute value of adjacent sampling points in the dimensionless voltage sequence, and carrying out weighted calculation in combination with the time distance from the current sampling point to the peak moment to obtain a waveform oscillation entropy index representing the waveform microcosmic oscillation degree. According to the method, more than 98% of neutron tube ignition interference can be effectively eliminated, the high-energy part of the energy spectrum is remarkably purified, and the problem that data of the aged neutron tube are unavailable is solved.

The invention discloses a control method and device of a material moisture online monitoring system and a storage medium, and relates to the technical field of material moisture monitoring, and the method comprises the steps: starting a neutron generator assembly, and starting a neutron detector assembly and a gamma detector when the starting duration of the neutron generator assembly is greater than or equal to the preheating preset duration; based on a detection result of the neutron detector assembly, determining an accumulated scattering neutron share of the detected material, and obtaining a corresponding target hydrogen density matched with the accumulated scattering neutron share from a preset association library; based on a gamma detector, counting the monitored gamma rays in a classified manner according to the pulse amplitude, generating a gamma-ray energy spectrum, and extracting a water hydrogen characteristic peak area from the gamma-ray energy spectrum; according to the target hydrogen density, the water-hydrogen characteristic peak area and the energy spectrum calibration coefficient of the gamma-ray energy spectrum, the curing hydrogen ratio is determined; and determining the free water content of the detected material according to the cured hydrogen ratio. According to the invention, through dual-mode cooperative detection, the problem of low accuracy of moisture monitoring is solved.

The invention belongs to the technical field of nuclear power plant subcritical degree determination, and particularly relates to a method for determining a subcritical degree by adopting a spatial effect of an external neutron source. Comprising the following steps: 1, obtaining a curve of the ratio of the subcritical degree to near-source and passive neutron detector signals through theoretical calculation; 2, obtaining measurement values of four source range neutron detectors and four intermediate range neutron detectors; 3, calculating a near-source and passive ratio; and 4, according to the ratio calculated in the step 3, searching a ratio curve of the subcritical degree and the signals of the near-source and passive neutron detectors so as to obtain the reactivity of the reactor core. The method has the beneficial effect that the subcritical degree cannot be obtained by directly measuring through an instrument when the power level of the reactor is lower. According to the method, the subcriticality can be quickly obtained in a chart form through the ratio of the near-source neutron detector signals to the passive neutron detector signals or the ratio of the passive neutron detector signals to the near-source neutron detector signals.

The invention discloses a blended neutron / gamma discrimination polysiloxane scintillator and a preparation method thereof. The polysiloxane scintillator is composed of a matrix, a primary fluorescent dye, a secondary fluorescent dye and a cross-linking agent. A matrix of the scintillator is a copolymer of methyl phenyl polysiloxane and phenyl methyl siloxane, a main fluorescent dye is 2, 5-diphenyl oxazole (PPO), a secondary fluorescent dye is selected from 7-diethylamino-4-methylcoumarin (MDAC), and a cross-linking agent is 1, 3-divinyl-1, 3-diphenyl-1, 3-dimethyl siloxane. The obtained polysiloxane scintillator has good stability and can be used for neutron detection and neutron / gamma discrimination in a strong irradiation field environment.

The invention discloses a sensitivity coefficient calculation and fitting method for a self-powered neutron detector of a nuclear reactor, which comprises the following steps of: 1, performing component calculation under different burn-up depths and working condition parameter conditions by using a nuclear reactor component program to obtain neutron flux density and fuel component linear power density at the self-powered neutron detector under corresponding conditions; secondly, current signals generated by the self-powered neutron detector under different working condition parameters are calculated through a Monte Carlo program; thirdly, the relation between the linear power density of the fuel assembly and a current signal generated by the self-powered neutron detector is established, and the sensitivity coefficient of the self-powered neutron detector is obtained; fourthly, performing function fitting on the sensitivity coefficient of the self-powered neutron detector with respect to the burn-up depth and the working condition parameters to obtain a fitting coefficient; according to the method, the mapping relation between the current signal of the self-powered neutron detector of the nuclear reactor and the linear power density of the fuel assembly is effectively established, and key technical support is provided for online monitoring of the nuclear reactor.

The application discloses a double-gas-chamber neutron detector, belonging to the technical field of nuclear radiation detection and particle detection, comprising a gadolinium film neutron conversion layer, two time projection chamber (TPC) modules and an optional energy quantifier module. After capturing thermal neutrons, the gadolinium film generates multi-state particles, and the two TPC modules realize 4π solid angle neutron detection through electronic signal coincidence. The application replaces the scarce 3 He with gadolinium, combines the track reconstruction capability of the double TPC module, significantly improves the neutron detection efficiency and signal-to-noise ratio, and is suitable for nuclear reactor monitoring, industrial material analysis, agricultural moisture detection and deep space exploration and other fields. Through electronic-gamma coincidence measurement and mode recognition, high-precision neutron signal reconstruction and environmental background suppression are realized.

The invention provides a device and a method for on-line measurement of boron concentration in a boron trifluoride complex system, and relates to the technical field of boron-10 acid production. The device comprises a neutron emission part, a fluid circulation part, a neutron detection part and a data processing part. The neutron emission part is used for emitting thermal neutron beams, the fluid circulation part is communicated with a fluid pipeline at the bottom of an exchange rectifying tower of the boron trifluoride-anisole complex production process, and the fluid circulation part is of a neutron penetrable structure; the neutron detection part is arranged on the side, away from the neutron emission part, of the fluid circulation part and used for receiving thermal neutron beams penetrating through the boron trifluoride-anisole complex and converting neutron intensity signals into electric signals, and the data processing part is electrically connected with the neutron detection part and used for receiving the electric signals and sending the electric signals to the fluid circulation part. And inverting the concentration of boron-10 in the boron trifluoride-anisole complex according to the attenuation degree of the thermal neutron beam to obtain the total concentration of boron. The device can output the total boron concentration measurement result in real time, and sampling can be carried out without interrupting the production process.

A neutron spectrometer collimator system includes a first collimator, a first mounting frame, and a position adjustment device. The first collimator is arranged between the center point of the sample and the neutron detector, and the first collimator is mounted on the first mounting frame, and the first mounting frame is mounted on the position adjustment device. The first collimator is used to collimate the diffracted neutron beam to effectively reduce the entry of stray neutrons into the neutron detector. At the same time, the position adjustment device can adjust the position of the first collimator to find the position with the largest flux of the diffracted neutron beam, so as to reduce the background noise, enhance the effective signal, increase the signal-to-noise ratio, and improve the experimental resolution and accuracy of the spectrometer.

A method of deploying a pulsed neutron logging tool. The method may comprise detecting natural gamma rays from the subterranean formation via one or more detectors of the pulsed neutron logging tool, broadcasting neutrons into the subterranean formation, and detecting neutron-induced gamma rays and natural gamma rays from the subterranean formation. The method may further comprise creating an inelastic spectrum, a capture spectrum, or a capture time decay from the natural gamma rays or the neutron-induced gamma rays, forming an inelastic yields, a capture elemental yields, or a formation sigma form the inelastic spectrum, the capture spectrum, or the capture time decay, creating a closure model from the inelastic yields and / or capture elemental yields and / or a formation sigma, and identifying a porosity, a mineral weight fraction, or a quality figure of merit from the closure model that quantifies geologic hydrogen reservoir quality.

The application discloses a same-position integrated double neutron detector, a logging instrument and an application method, and belongs to the field of uranium ore exploration logging. The double neutron detector comprises first and second scintillation crystals which are both sensitive to thermal neutrons and are arranged in a face-to-face manner, a photoelectric converter and a supporting portion; the first and second scintillation crystals and the photoelectric converter are arranged along the same axis to form a detection portion which is read out by a common light path, and the supporting portion is fixedly arranged outside the detection portion and supports the detection portion to be an integral component; a slow moderation layer is arranged on the outer wall surface of the first scintillation crystal except the bonding area; the logging instrument is provided with the double neutron detector, and the first and second scintillation crystals are calibrated in the same thermal neutron field during application; the spatial consistency error is eliminated through the same-position design of the double scintillation crystals; the hardware structure of the detector electronics is simplified through the common light path reading out design; and the detector module is convenient to integrate.

The preparation method of the heterojunction device comprises the steps that a boron nitride thin film is prepared with ammonia borane as a precursor, then a gallium nitride layer grows on the boron nitride thin film to form a heterojunction structure, and the ratio of the usage amount of the ammonia borane to the area of a substrate is 150 mg / cm < 2 > to 250 mg / cm < 2 >. According to the preparation method provided by the embodiment of the invention, a high-quality BN-GaN heterojunction neutron device can be provided, and a foundation is laid for research, development and application of a novel neutron detector for replacing a 3He tube. Ammonia borane is non-toxic, non-flammable and non-explosive at normal temperature, is stable and easy to store, has a stoichiometric ratio of B / N of 1: 1, is relatively low in decomposition temperature and pollution-free in decomposition product, can be used as a boron source and a nitrogen source, and is a single precursor. The quality of the heterojunction device is guaranteed, the production cost is reduced, and the heterojunction device has the advantages of simple structure, relatively small size, good linear range, short response time, easy n / gamma discrimination, high detection efficiency and the like.

The invention provides a neutron detector availability evaluation method, system, equipment and medium, and relates to the technical field of nuclear power plant ex-core nuclear instrumentation system debugging and operation and maintenance, and the evaluation method comprises the steps: obtaining a high-pressure characteristic curve of a neutron detector in a current fuel cycle period; according to the high-pressure characteristic curve, acquiring the plateau inclination of the neutron detector in the current fuel circulation period; according to the high-voltage characteristic curve, the current power level of the reactor, the power level upper limit required to be measured by the neutron detector, the working voltage of the neutron detector and the voltage upper limit of the low-voltage area of the neutron detector, obtaining the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel circulation period; and determining the availability of the neutron detector according to the plateau slope and the voltage margin of the high-voltage characteristic curve. According to the evaluation method, system, equipment and medium provided by the invention, the availability of the current neutron detector can be comprehensively evaluated and the residual service life of the neutron detector can be predicted on the premise of not changing out-of-core nuclear instrumentation system equipment.

The present disclosure provides a neutron detector and a neutron detection method. The neutron detector comprises an absorption layer and a photoelectric detection device, wherein: the absorption layer comprises at least one gamma sensitive layer and at least one neutron sensitive layer, the neutron sensitive layer is embedded in the first side of the gamma sensitive layer, wherein: the to-be-detected neutron and the gamma background of the to-be-detected neutron are incident from the second side of the gamma sensitive layer, the first side is opposite to the second side, the gamma background deposits energy in the gamma sensitive layer to generate first scintillation light, and the to-be-detected neutron deposits energy in the neutron sensitive layer to generate second scintillation light; the photoelectric detection device is arranged on the first side of the gamma sensitive layer embedded with the neutron sensitive layer, and is used for detecting the first scintillation light and the second scintillation light, so as to realize the detection and discrimination of the to-be-detected neutron and the gamma background. The method realizes the improvement of the discrimination effect of neutron events and gamma events.

The invention discloses a growth method of an organic-inorganic hybrid two-dimensional phenylethylamine lead bromide perovskite single crystal, relates to a growth method of a phenylethylamine lead bromide perovskite single crystal, and aims to solve the technical problems of long growth period and small thickness of the existing two-dimensional phenylethylamine lead bromide single crystal. The method comprises the following steps: 1, obtaining seed crystals; 2, thermodynamically regulating and controlling the solution supersaturation degree by a constant-temperature water bath device; 3, seed crystal growth is dynamically regulated and controlled through a seed crystal rotating-gradient cooling method under the solution rotating condition, the phenylethylamine lead bromide perovskite single crystal is obtained, the length and width of the phenylethylamine lead bromide perovskite single crystal are larger than 2 cm, the thickness of the phenylethylamine lead bromide perovskite single crystal is larger than 2 mm, fast neutron detection and high-energy nuclear particle screening can be met, and the phenylethylamine lead bromide perovskite single crystal is applied to the field of nuclear radiation detectors.

This invention provides a method, system, device, and medium for assessing the availability of a neutron detector, relating to the field of commissioning and maintenance technology for external nuclear instrumentation systems in nuclear power plants. The assessment method includes: obtaining the high-pressure characteristic curve of the neutron detector for the current fuel cycle; obtaining the plateau slope of the neutron detector for the current fuel cycle based on the high-pressure characteristic curve; obtaining the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage of the neutron detector, and the upper limit of the low-pressure region voltage of the neutron detector; and determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-pressure characteristic curve. The assessment method, system, device, and medium provided by this invention can comprehensively assess the current availability of the neutron detector and predict its remaining service life without changing the external nuclear instrumentation system equipment.

The invention relates to a detector array and a detection device for marking neutron beam imaging, a plurality of detector units in the array are arranged at intervals, a vacancy unit is arranged between every two adjacent detector units, each detector unit is a multi-pixel neutron detector with a scintillator array, and the scintillator array is arranged between the detector units. The scintillator array can realize n / gamma discrimination. Crosstalk of neutron signals among the scintillation units can be reduced, interference of background gamma signals can be effectively eliminated, the light collection capacity and the resolution capacity of edge points of the scintillator array can be improved through the special light guide structure design, and height adjustment and angle adjustment of the detector array can be achieved through the detector support.

This invention discloses a U-shaped neutron detection device for detecting the burn-up depth of spent fuel, belonging to the field of non-destructive testing technology for high-level radioactive spent fuel. It includes: two opposing arm detection components; a back detection component; each arm detection component includes: a moderator material; multiple arm He-3 counters spaced apart within the moderator material; a gamma shield disposed on the outer wall of the moderator material; and a cadmium sheet disposed on the outer wall of the other side of the moderator material; the back detection component includes: a support material, with both ends of the support material fixedly connected to the ends of the two moderator materials; multiple back He-3 counters spaced apart within the support material; a base plate disposed on the outer wall of the support material; and a cable connection assembly disposed on the side of the base plate away from the spent fuel component to be measured. This invention provides dual protection for the measurement of spent fuel burn-up depth by utilizing fission neutron information and transmitted neutron information, meeting the requirements for online detection.

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

This application discloses a control method, device, and storage medium for an online material moisture monitoring system, relating to the field of material moisture monitoring technology. The method includes: starting a neutron generator assembly; when the start-up time of the neutron generator assembly is greater than or equal to a preset preheating time, activating a neutron detector assembly and a gamma detector; determining the cumulative scattered neutron share of the measured material based on the detection results of the neutron detector assembly, and obtaining the cumulative scattered neutron share to match the corresponding target hydrogen density from a preset correlation library; generating a gamma spectrum based on the gamma rays monitored by the gamma detector according to pulse amplitude classification and counting, and extracting the water hydrogen characteristic peak area from the gamma spectrum; determining the solidified hydrogen ratio based on the target hydrogen density, the water hydrogen characteristic peak area, and the energy spectrum calibration coefficient of the gamma spectrum; and determining the free water content of the measured material based on the solidified hydrogen ratio. This application solves the problem of low accuracy in moisture monitoring through dual-modal collaborative detection.

The invention discloses a neutron detection device and a neutron logging system.The neutron detection device comprises a neutron detection tube and a circuit board, the neutron detection tube is used for responding to neutron radiation and generating electric signals, the circuit board is arranged at one end of the neutron detection tube, and the signal output end of the neutron detection tube is connected with the input end of the circuit board; the circuit board is provided with an analog-to-digital conversion circuit, and the analog-to-digital conversion circuit is used for carrying out digital sampling on the electric signals to output digital signals. According to the neutron detection device, the circuit board is arranged at one end of the neutron detection tube, the circuit board is provided with the analog-to-digital conversion circuit, electric signals generated by the neutron detection tube can be digitally sampled and converted into digital signals to be transmitted, and compared with a traditional neutron detection device which transmits the electric signals generated by the neutron detection tube in an analog signal mode, the signal transmission efficiency is improved; the digital signal is not easy to introduce noise and is not easy to be interfered, so that the stability, the accuracy and the anti-interference performance of measurement can be improved.

The invention discloses a measuring rod and an over-drill-bit measurement-while-drilling device and method. The measuring rod is provided with at least three expansion jackets at intervals in the radial direction, and any two expansion jackets and at least one part of the underground side wall form a measuring cavity after expansion. A liquid injection hole is formed in the part, in the measuring cavity, of the measuring rod, and a liquid injection channel communicated with the liquid injection hole is formed in the measuring rod in the radial direction; the measuring rod is provided with a measuring cabin between two adjacent expansion jackets, and the measuring cabin is at least integrated with a pressure sensor and a neutron detection assembly; the pressure sensor is used for collecting the pressure in the measuring cavity; the neutron detection assembly is used for measuring stratum parameters in the measurement cavity in a pressurized state. The multiple expansion jackets are used for forming the measuring cavities with different lengths so as to eliminate sealing failure caused by irregular borehole diameters, or the multiple expansion jackets are used for forming the multiple spaced measuring cavities so as to reduce the trust risk of a single data source, and a pressure sensor, neutron detection and the like are used for measuring stratum data in a pressurized environment.

This invention discloses a neutron analysis physics testing system and method, belonging to the field of nuclear physics testing technology. The system includes: a high-speed synchronous pulse generator for generating pulse signals with multiple modulation sequences; an ultrashort pulse neutron generator for emitting short pulse neutron rays with specified parameters onto a sample; a neutron detector for acquiring secondary neutron signals; a gamma detector for acquiring characteristic gamma signals generated by neutron-excited probes of the sample; a safety control module for controlling the operating state of the ultrashort pulse neutron generator; and a data processing device for real-time collection and summarization of neutron signals and characteristic gamma signals based on the timing of the pulse signals with multiple modulation sequences. This system reduces time window drift and measurement errors, and activates the ultrashort pulse neutron generator only when a gate signal allows, improving the accuracy, safety, and stability of geological physics parameter measurements.