82 results about "Neutron detection" patented technology

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 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 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 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 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.

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.

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.

The invention relates to the technical field of ionizing radiation measurement, and discloses a delayed neutron detector calibration device and method. The delayed neutron detector calibration device comprises a box body, a point neutron source and a moving assembly. An independent working cavity and an independent mounting cavity are defined by the box body. And the point neutron source is arranged in the mounting cavity. The moving assembly is arranged in the box body, the connecting end of the moving assembly extends into the working cavity, and the connecting end of the moving assembly is connected with the detector. Wherein the moving assembly is used for driving the detector to move relative to the point neutron source, so that different positions of the detector correspond to the point neutron source, and the reading of the detector is obtained so as to perform segmented calibration on the detector. According to the method and the device, the delayed neutron detector can be calibrated on site, the time of the calibration implementation process of the delayed neutron detector is shortened, and the difficulty of the calibration implementation process of the delayed neutron detector is reduced.

The application discloses a method for quickly obtaining a steady-state space electric field of an insulation layer of a self-powered detector, and comprises the following steps: obtaining radiation field information and detector information at a position where a self-powered neutron detector is located, and simulating to obtain an electric charge deposition amount generated by irradiation current in different radius intervals per unit time of the detector; according to the law of conservation of electric charge, estimating an electric charge loss amount generated by conduction current in different radius intervals of an insulator per unit time under a steady-state condition; combining Ohm's law to establish an expression of the electric charge loss amount generated by the conduction current about an electric field intensity under the steady-state condition, and combining a boundary condition to obtain an electric field intensity distribution, an electric charge density distribution and a potential distribution. The application can effectively improve the calculation efficiency and realize efficient simulation of the sensitivity of the self-powered neutron detector.

The invention discloses a neutron analysis physical testing system and method, and belongs to the technical field of nuclear physical testing. The system comprises a high-speed synchronous pulse generator used for generating pulse signals of various modulation sequences; the ultrashort pulse neutron generator is used for emitting short pulse neutron rays with specified parameters to the sample; the neutron detector is used for acquiring a secondary neutron signal; the gamma detector is used for acquiring a characteristic gamma signal generated by the neutron excitation detection sample; the safety control module is used for controlling the working state of the ultrashort pulse neutron generator; and the data processing device is used for collecting and gathering neutron signals and characteristic gamma signals in real time according to the time sequence of the pulse signals of the multiple modulation sequences. According to the system, time window drift and measurement errors are reduced, the ultra-short pulse neutron generator is started only under the condition that access control signals allow, and the accuracy, safety and stability of stratum physical parameter measurement are improved.

The invention relates to the technical field of data transmission control, in particular to a neutron detection data real-time preprocessing method and system based on edge calculation. The method comprises the following steps: acquiring an original energy spectrum data packet through a high-speed acquisition circuit of an underground instrument and temporarily storing the original energy spectrum data packet into a primary annular buffer area; calculating the geological disturbance index of the current frame data according to the counting difference of the current frame and the previous frame in the feature energy window and the full spectrum information entropy of the current frame; reading the occupancy rate of a communication sending buffer queue in real time, and calculating the dynamic transmission admission probability of the current frame data in combination with the geological disturbance index; and dynamically selecting a compression strategy and a transmission priority of the current frame data according to a comparison result of the dynamic transmission admission probability and a preset threshold value. The problem that key geological information is lost due to the fact that channel bandwidth is limited in deep well logging is solved, preferential fidelity transmission of high-value data is achieved through a coupling mechanism of geology and a channel, and the risk of cache overflow is eliminated.

The invention discloses a preparation method for growing large-size isotope hexagonal boron nitride at normal pressure and high temperature and application of the large-size isotope hexagonal boron nitride in neutron detection, and the method comprises the following steps: uniformly mixing nickel powder, chromium powder and boron powder to obtain a mixture of boron and nickel-chromium alloy; then carrying out deoxidation treatment under the protection gas flow; reducing the pressure of the system, introducing mixed gas of protective gas and reactive protective gas to normal pressure, and protecting; finally, the deoxidized mixture is subjected to secondary stepped heating, heat preservation is carried out after primary heating, and the temperature of primary heating is higher than that of secondary heating; and naturally cooling to room temperature to generate the hexagonal boron nitride crystal. According to the method, the nickel-chromium alloy is adopted as the metal fluxing agent, the large-size and high-quality isotope hexagonal boron nitride single crystal is successfully prepared under the normal pressure condition through the optimized gas atmosphere and stepped temperature control, and the method has important application value in the fields of neutron detection, two-dimensional materials and the like.

The application discloses a reactor neutron detector calibration method, system and computer equipment, relates to the nuclear reactor core monitoring technical field, and is based on the absolute neutron flux at a position of a reactor core measured by an activation method, combines the neutron flux distribution relation inside and outside the reactor, maps the absolute neutron flux at the position of the neutron detector outside the reactor, obtains the corresponding relation between the neutron detector measurement result and the absolute neutron flux at the neutron detector, and based on the corresponding relation and the neutron detector measurement result, the absolute neutron flux at the detector can be quickly and accurately obtained. The application only uses the activation method to calibrate the conversion factor of the neutron detector once, and under various conditions such as changes in the core arrangement, changes in the core control rod state, changes in the core power and the like, the absolute neutron flux at the detector can be directly obtained through the measurement result of the neutron detector, and multiple irradiation experiments are not needed, so that the measurement efficiency is improved, and the cost is saved.

According to the present invention, the in-core measuring instrument that provides both a core protection signal and a core monitoring signal includes a self-powered neutron detector (SPND) for measuring neutron flux, wherein the neutron detector (SPND) includes an emitter, a welding point, a signal wire, a sheath, an insulator, and a resin. The emitter of the neutron detector for measuring neutron flux includes a delayed-response rhodium (Rh) or vanadium (V) emitter and a prompt-response cobalt (Co) emitter, wherein the rhodium (Rh) or vanadium (V) emitter is used for core monitoring by detecting delayed electron generation after a predetermined time due to a half-life of a compound nucleus generated by a reaction with neutrons, and the cobalt (Co) emitter is used for core protection by detecting an immediate change in neutron flux of a core through prompt electron generation caused by a material reaction, the cobalt (Co) emitter being used for core protection against rapid heating or cooling of the core by detecting a change in the temperature difference (ΔT) between a core inlet thermocouple (CIT) and a core outlet thermocouple (CET). A nuclear fuel assembly includes a nuclear fuel rod, a nuclear fuel control rod guide tube, and an in-core measuring instrument guide tube positioned at a central portion where the nuclear fuel rod and the nuclear fuel control rod guide tubes are arranged. The in-core measuring instrument, which is disposed in the in-core measuring instrument guide tube and includes two types of neutron detectors for measuring neutron flux and two thermocouples for measuring core inlet temperature and core outlet temperature, is configured to simultaneously perform core protection and core monitoring by measuring neutron flux, perform core protection by using a core inlet–outlet temperature difference (ΔT), and calibrate neutron flux measured by the cobalt emitter using the rhodium or vanadium emitter.

A multi-use incore system for use with a nuclear reactor having a reactor core including an instrumentation tube is disclosed. The multi-use incore system comprises a drive cable, a neutron detector, an electromagnetic tool, and an irradiation target. The drive cable comprises an adapter at its distal end. The drive cable is slidably receivable into the instrumentation tube. The neutron detector is removably attachable to the adapter of the drive cable to monitor core power distribution. The neutron detector is slidably receivable into the instrumentation tube by the drive cable. The electromagnetic tool is removably attachable to the adapter of the drive cable in lieu of the neutron detector. The irradiation target is to produce a radioisotope. The drive cable is selectively attachable to the irradiation target by the electromagnetic tool to insert the irradiation target into the instrumentation tube and remove the irradiation target from the instrumentation tube.

This invention discloses an online location method for abnormal components within the reactor based on neutron noise analysis. This method utilizes the detection signals from existing neutron detectors within the reactor for online analysis, eliminating the need for additional detectors. It combines the theoretical neutron noise spectrum of each component, calculated in advance for high-risk components that may have loosening, detachment, or local boiling within the reactor, with an in-reactor abnormal component location algorithm to provide real-time directional location of the abnormal components. This provides early warning information for reactor operation monitoring and fault diagnosis, and has significant implications for the safe operation of reactors and the construction of diagnostic systems.

The invention provides a hybrid neutron detector and a neutron / gamma discrimination method thereof, and relates to the field of neutron detection. The hybrid neutron detector comprises a counting tube, a signal acquisition and processing module, a control unit and a voltage switching module, the counting tube comprises a hollow tube body, an anode, a cathode and an insulating ring, the anode is in sealed connection with one end of the tube body through the insulating ring, the cathode is in sealed connection with the other end of the tube body through the insulating ring to form a sealed cavity, and a gap is formed between the anode and the cathode; the surface of one end, close to the anode, of the cathode is a rough surface; a scintillation coating is arranged on the inner wall of the tube body; the sealed cavity is filled with sensitive gas containing 10B nuclide; the cathode is connected with the input end of the signal acquisition and processing module, and the output end of the signal acquisition and processing module is connected with the input end of the control unit; and the voltage switching module is connected with the anode. The neutron detector has excellent neutron / gamma discrimination capability and higher radiation damage resistance and is low in cost.

This invention discloses a method for preparing a multi-level micro / nano-structured composite material for nuclear radiation detection, relating to the field of nuclear radiation detection technology. Specifically, it utilizes gold-sulfur self-assembly technology to modify the surface of a gold nanoparticle core with boron-containing molecules, obtaining a functionalized gold nanoparticle core. This core is then used as a seed, with chloroauric acid as the gold source, to grow a gold nanoshell. Finally, silver nitrate is used as the silver source to deposit a silver nanoshell in situ, resulting in a multi-level micro / nano-structured composite material. This multi-level micro / nano-structure uses gold nanoparticles as the core, boron-containing molecules as the neutron detection medium, the gold nanoshell as the surface-enhanced Raman scattering (SERS) carrier, and the silver nanoshell as the gamma-ray detection medium. This material possesses both neutron and gamma-ray detection capabilities, and the neutron response of the boron-containing molecules and the gamma-ray response of the silver nanoshell can be quantitatively measured using SERS and LSPR spectroscopy, respectively. This enables efficient discrimination of mixed radiation field doses and has broad application prospects in the field of nuclear radiation detection.

A signal processing method and device of a fast neutron detection device, electronic equipment and medium, which acquires a waveform signal output by a preamplifier of the fast neutron detection device and continuously samples to obtain a discrete sampling signal; determines a baseline mean, a baseline standard deviation and a slope standard deviation during the continuous sampling process, and determines an amplitude trigger threshold and a slope trigger threshold accordingly; jointly triggers through an amplitude condition and a slope condition to determine a trigger time; intercepts an event window from the cached signal based on the trigger time, and calculates event characteristics such as a peak amplitude, a rising edge slope, a pulse width characteristic, a negative polarity proportion and a zero-crossing number according to a signal amplitude sequence in the event window; discriminates the event characteristics according to a preset rule set and determines a comprehensive score to distinguish effective fast neutron events and false pulses; and outputs a fast neutron counting result according to the effective fast neutron events. The present application can reduce false triggering caused by microphone interference, ringing and baseline drift, and improve the reliability of the fast neutron counting result.

The invention discloses a microminiature static liquid fuel reactor and a noiseless thermoelectric conversion method thereof, and belongs to the technical field of nuclear engineering. The reactor core comprises a reactor core body filled with liquid fission fuel; the natural negative feedback system comprises a first negative feedback unit formed by the thermal expansion effect of the liquid fission fuel and a second negative feedback unit formed by a plurality of gas expansion modules; the thermoelectric conversion system comprises a heat pipe in direct contact with the liquid fission fuel and a thermoelectric conversion assembly integrated on the heat pipe; the sensing and control system comprises a plurality of temperature sensors and neutron detectors, a control rod, a driving mechanism and a control system; wherein the control system judges whether the adjustment of the natural negative feedback system is sufficient or not based on the monitoring data of the temperature sensor and the neutron detector, and regulates and controls the position of the control rod when the adjustment is judged to be insufficient so as to maintain the stable power of the reactor core, and the high-reliability operation of the reactor in the whole life period can be ensured.

The application 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, which comprises the following steps: collecting, by a neutron detector and a neutron generator, the count rate, the neutron fluence rate and the data of each kind of environmental parameter around the reference radiation field at each time in each monitoring period; regarding each monitoring period and a plurality of monitoring periods before the monitoring period as each historical period; determining the measurement error degree of each historical period; obtaining the measurement interference degree of each kind of environmental parameter under each monitoring period; calculating the scattering interference degree of each kind of environmental parameter under each monitoring period, obtaining the calibration count rate and performing real-time calibration on the neutron fluence response. The application can quantize the interference influence of different environmental factors on the measurement result of the neutron detector through dynamic environmental changes, calibrate the measurement result of the neutron detector in real time and improve the measurement accuracy of the neutron fluence response.

A kind of miniature neutron detector conical surface light-concentrating heat-resistant probe, its characteristics include luminous body, light-concentrating cylinder, light-concentrating lens, armored shell, fixing sleeve, compression spring, set screw and optical fiber;Flasher material is made into cylindrical luminous body by using capillary glass tube, the volume of flasher material increases, the neutron activation reaction of flasher material is more sensitive, the light-emitting surface area increases, effectively improve the number of photons generated by flasher material, then light emitted by luminous body is collected, refracted and converged by light-concentrating cylinder and light-concentrating lens, compared with traditional detector probe, effectively reduce the light attenuation of light signal in the process of optical fiber transmission due to random angle incidence, different energy level photon distribution is more uniform and concentrated, the signal strength after conversion is strong, signal pulse accumulation is less, it is easier to be read, greatly improve the detection efficiency of detector, have good enlightenment effect on the technical problems faced by the field, have good popularization and application value.

The invention relates to the technical field of signal processing of neutron detectors, in particular to a neutron pulse signal collecting and counting device and method. According to the technical scheme, the neutron detector comprises a front signal source, a low-noise signal amplifier, an analog-to-digital conversion module and a signal collecting and processing unit, and the front signal source adopts a microstructure semiconductor neutron detector and is used for receiving neutron radiation and generating charge pulse signals; and the low-noise signal amplifier is connected with the front signal source and is used for amplifying the charge pulse signal. A set of complete neutron signal acquisition and processing system is constructed by integrating a microstructure semiconductor neutron detector, a three-stage low-noise amplification circuit, a high-speed analog-to-digital conversion module based on double-ADC alternate sampling and a self-adaptive digital processing algorithm, so that high sensitivity, low-noise amplification and high-speed sampling are realized, and the detection accuracy is improved. The method has excellent pulse identification precision and real-time energy spectrum reconstruction capability.

The invention discloses a same-position integrated double neutron detector, a logging instrument and an application method, and belongs to the field of uranium exploration logging. The double-neutron detector comprises a first scintillation crystal, a second scintillation crystal, a photoelectric converter and a supporting part, wherein the first scintillation crystal and the second scintillation crystal are sensitive to thermal neutrons and are arranged in a face-to-face fitting manner; the first scintillation crystal, the second scintillation crystal and the photoelectric converter form a common-optical-path read-out detection part along the same axial direction, and the supporting part is fixedly arranged on the outer side of the detection part and supports the detection part to form an integral component; a shielding slowing-down layer is arranged on the outer wall surface of the first scintillation crystal except the fitting area; the logging instrument is provided with the double-neutron detector, the first scintillation crystal and the second scintillation crystal are calibrated in the same thermal neutron field when the logging instrument is applied, the space consistency error is structurally eliminated through the same-position design of the double scintillation crystals, the electronic hardware structure of the detector is simplified through the common-path reading design, and the detector module is convenient to integrate.