3716 results about "Nuclear engineering" patented technology

The invention discloses a processing method of a fusion device, and belongs to the technical field of nuclear fusion. The processing method comprises the following steps: carrying out at least one time of vacuum heat treatment on a Dewar embedded part blank; carrying out cleaning anti-corrosion treatment and physical correction treatment on the surface of the dewar embedded part blank subjected to heat treatment; carrying out grinding and polishing treatment on the surface of the Dewar embedded part blank subjected to the cleaning and antiseptic treatment and the physical correction treatment to obtain the Dewar embedded part; the Dewar embedded part is transported to the installation position of the window to be installed, and the Dewar embedded part located at the installation position is temporarily fixed; performing concrete pouring on the mounting position of the Dewar embedded part; and after the concrete is solidified, a cast-in-place concrete structural body is formed in the area below the Dewar embedded part, and a part of the Dewar embedded part is embedded into the cast-in-place concrete structural body. By means of the method, the magnetic conductivity of the Dewar embedded part is reduced, and the risk that elements are activated to form isotopes with the long decay period and the high irradiation dose rate or isotopes with the short decay period and the high irradiation dose rate is reduced.

The invention discloses a method and tool for manufacturing a cold shield of a nuclear fusion device, and relates to the technical field of metal plate machining. The manufacturing method of the cold shield of the nuclear fusion device comprises the following steps: providing a sub-panel, a flange and a pipe fitting; the multiple sub-panels are welded, and a first middleware is obtained; welding the edge of the first middleware and the turnup to obtain a second middleware; after the pipe fitting is welded to the surface of the second middleware, a third middleware is obtained; and the third middleware is shaped. According to the method, the third middleware is shaped, that is, the third middleware is shaped after all welding procedures are completed, so that the third middleware has relatively small profile tolerance, the profile tolerance of the cold shield meets the design requirement, the assembly difficulty of the cold shield is reduced, and the risk of failure of the cold shield is reduced.

The invention discloses an ocean in-situ radioactivity monitoring method, which is characterized in that feature extraction is carried out based on a maximum likelihood expected value maximization (MLEM) algorithm, and spectrum unfolding operation is carried out by adopting a multi-layer perceptron. The method comprises the following steps: firstly, measuring FWHM related parameters of a CeBr3 detector by adopting a standard source, simulating the response of the detector to gamma rays in a marine environment based on a Monte Carlo method, and establishing a full-spectrum response matrix H in a range of 0-2048keV; based on the response matrix H, reconstructing a gamma energy spectrum y obtained by the detector by using an MLEM iterative algorithm; and the reconstructed spectrum is used as the input of a multi-layer perceptron (MLP), and qualitative and quantitative analysis of radionuclides in the energy spectrum is realized. According to the method, the discrete characteristic peak signal is convolved into the single path address corresponding to the characteristic energy, so that the accuracy of the MLP model in the spectrum unfolding process is effectively improved.

The invention discloses a BNCT dose calculation method, which comprises the following steps: S1, constructing a voxel model, initializing one or more particles in a simulation system, and respectively acquiring the initial position, energy and movement direction of each particle; s2, adaptively selecting a Monte Carlo particle tracking algorithm and a flux counting mode based on the region where the particles are located and the energy of the particles; s3, repeating the step S2 until the particles leave the simulation system or are killed when meeting a truncation condition; and S4, cumulatively calculating dose distribution. Through the BNCT dose calculation method, the Monte Carlo particle transport simulation time is greatly shortened, the BNCT dose calculation efficiency is optimized, and the method is suitable for rapid and high-precision radiation dose simulation under a BNCT complex tissue structure.

The invention relates to the technical field of gamma-ray spectrum analysis, particularly provides a gamma-ray detector activation analysis method and a PGNAA detection system, and aims to solve the problems that gamma rays obtained by detection of an existing gamma-ray detector comprise rays generated by decay of crystals after activation in a neutron field; therefore, the component detection result of the to-be-detected sample is not accurate. In order to achieve the purpose, the activation analysis method for the gamma detector comprises the steps that a to-be-detected sample is irradiated through a neutron source; repeatedly collecting a plurality of groups of gamma-ray energy spectrums of the sample to be detected by using a gamma-ray detector; constructing an energy spectrum signal matrix based on the gamma-ray energy spectrum of the to-be-detected sample, wherein the energy spectrum signal matrix is a mixed signal composed of instant gamma rays generated by neutron activation of the to-be-detected sample, environmental background gamma rays and interference signals generated by crystal activation in a gamma detector; and obtaining the effective instant gamma ray based on the energy spectrum signal matrix. The self-interference influence of the detector is effectively reduced, and the target element content evaluation precision of the to-be-detected object is improved.

The invention relates to the technical field of Tokamak nuclear fusion, and discloses an assembling method of a pre-assembled assembly of a nuclear fusion device and an installing method of the nuclear fusion device. The pre-assembled assembly comprises a vacuum chamber, a window neck tube in the vacuum chamber, a vacuum chamber cold shield and a TF magnet; the assembling method of the nuclear fusion device preassembled assembly comprises the following steps: supporting between a cold shield inner sector and a vacuum chamber through a first tool; a first tool is supported between the cold shield outer sector and the vacuum chamber; the TF magnet is connected with the middle window position of the vacuum chamber through a second tool, the upper arc-shaped section of the outer fan section of the cold shield is connected with the hoisting tool of the TF magnet through a third tool, and the lower window section of the outer fan section of the cold shield is connected with the second tool; and the middle window section and the annular field magnet supporting seat are connected through a fourth tool. According to the assembling method of the nuclear fusion device pre-assembled assembly, interference among installation of the vacuum chamber, the window neck tube in the vacuum chamber, the vacuum chamber cold shield and the TF magnet can be avoided, and the stability and functionality of the pre-assembled assembly structure are guaranteed.

A cooling system for vehicles and a control method thereof improves indoor heating performance and fuel efficiency by controlling a flow rate of a coolant passing through a heater core together with an EGR cooler. A coolant having an increased temperature is first supplied to the heater core side through a flow stagnancy control to rapidly increase the temperature of the coolant flowing in the heater core, thereby improving heating performance. A warm-up feature is improved through an exhaust heat recovery function by a heat exchange between the exhaust gas and the coolant in the EGR cooler, thereby improving efficiency of fuel.

The invention provides a liquid cooling impurity monitoring method and system, and the method comprises the steps: obtaining an existing liquid cooling impurity attribute set through spectral analysis and microscopic imaging, deploying an impurity detection module in a liquid cooling channel, and obtaining a resonance spectrogram of the liquid cooling channel and environment parameters of the liquid cooling channel; performing cooperative feature extraction on the liquid-cooling cold channel resonance spectrogram and the liquid-cooling cold channel environment data, generating a liquid-cooling ecological vector, obtaining a historical liquid-cooling ecological vector corresponding to the historical data of the liquid-cooling cold channel, constructing a liquid-cooling impurity monitoring model, performing model pre-training to generate a liquid-cooling impurity library, inputting the liquid-cooling ecological vector to the liquid-cooling impurity monitoring model, and obtaining a liquid-cooling impurity monitoring result. Performing liquid cooling impurity matching on the liquid cooling ecological vector and a liquid cooling impurity library based on a cuckoo algorithm to obtain a liquid cooling impurity combination vector, obtaining a pre-trained impurity purification decision model, inputting the liquid cooling impurity combination vector into the impurity purification decision model, and generating an optimal liquid cooling impurity purification strategy, and a user can perform impurity removal on the liquid cooling system according to the optimal liquid cooling purification strategy.

A positron emission tomography (PET) scanner includes a plurality of gamma radiation detector modules arranged to form a detector ring. Each detector module includes an array of scintillator detectors. Each scintillator detector comprises a monolithic scintillation crystal and a plurality of photodetector arrays, such as silicon photomultipliers (SiPMs). A photodetector array is positioned on at least two nonparallel faces of each scintillation crystal. In some examples, a photodetector array is positioned on each of three orthogonal faces of each scintillation crystal.

The invention relates to the technical field of CLYC neutron-gamma rays, and provides a CLYC neutron-gamma ray screening detection method and device based on deep learning, and the method comprises the steps: carrying out the preprocessing of an original pulse waveform outputted by a CLYC detector, and obtaining clean standard waveform data; constructing a one-dimensional convolutional neural network model, respectively capturing the features of the waveform at different time scales, and identifying the most discriminative feature region in the waveform through an attention mechanism; performing adaptive adjustment on the original hyper-parameter of the one-dimensional convolutional neural network model to obtain an optimized hyper-parameter; establishing a direct mapping relation from an original pulse waveform to a neutron-gamma particle type to obtain a trained model; and carrying out compression optimization processing on the model, and deploying the model to an embedded platform to carry out neutron-gamma ray discrimination. According to the method, automatic extraction of deep discrimination features of the CLYC pulse waveform and accurate identification of key feature areas are realized, and the discrimination accuracy and noise interference resistance of neutron-gamma rays are improved.

Main characteristic of the invention is the exploitation of the very large flux of high energy neutrons generated in a nuclear fusion tokamak with beam-driven plasma for the purpose of producing radioisotopes. It specifically relates to the deployment of precursor materials into the core of a nuclear fusion tokamak with beam-driven plasma for the purpose of exposing these materials to the neutron flux generated in the plasma by the process of nuclear fusion of Deuterium (D) and Tritium (T) to generate radioactive isotopes, so-called radioisotopes. The precursor materials contained in metallic capsules are incorporated into the blankets that surround the plasma.

The invention discloses an ion source automatic beam adjusting method, a radiotherapy system and related equipment, and relates to the technical field of radiotherapy, and the method comprises the steps: monitoring and adjusting a plurality of control parameters in real time, and obtaining an optimal control parameter combination; under the optimal control parameter combination, the variable quantity of each control parameter before and after adjustment and the performance change of the proton beam are obtained; performing a pulse width charge test according to the variation of each parameter before and after adjustment and the performance change of the proton beam; obtaining an optimal adjustment parameter and an adjustment amount through a pulse width charge test result; and through the optimal adjustment parameter and adjustment amount, automatic beam adjustment is realized, stable and efficient acceleration of the proton beam in the synchrocyclotron system is realized, and the stability and consistency of the proton beam are ensured.

The invention discloses a hybrid neutron gamma detector array and a signal processing method, and relates to the technical field of nuclear physical detection.During detection, eight EJ200 scintillators arranged in an array are used for energy deposition of gamma rays and fast neutrons and generating photons, and meanwhile three EJ426 thermal neutron scintillation screens are used for capturing thermal neutrons and generating photons; the response of gamma rays, fast neutrons and thermal neutrons is realized at the same time, and the detection precision is greatly improved. Meanwhile, if the three EJ426 thermal neutron scintillation screens are alternately stacked front and back, the total reflection of the EJ200 scintillators and the semi-light-proof performance of the EJ426 thermal neutron scintillation screens are utilized to block photon propagation in the X direction and only enable photons to be propagated in the Y direction and the Z direction, and each EJ200 scintillator corresponds to a four-channel photon collection structure to perform high-efficiency collection of the photons, so that the high-efficiency collection of the photons is realized. Therefore, high-precision detection and high-efficiency photon collection are realized, and support is provided for subsequent intense radiation field monitoring or high-precision positioning.

The invention provides a pencil beam dose calculation method. The pencil beam dose calculation method comprises the following steps: acquiring human body image data; determining a plurality of particle types for treatment; calculating initial pencil beam dose distribution corresponding to each particle type; based on the particle types, target action layers, distributed in the human body image data, of all the doses are determined, and the positions of the target action layers corresponding to different particle types are different; based on the target action layer corresponding to each particle type, adjusting each initial dose distribution, and obtaining particle pencil beam dose distribution corresponding to each particle type; superposing the particle pencil beam dose distribution corresponding to each particle type to obtain target pencil beam dose distribution; wherein the dose proportion of the particle pencil beam dose distribution corresponding to the same particle type in the target action layer is greater than the dose proportion of the particle pencil beam dose of the particle type in other parts in the human body image data.

The present invention relates to a heat exchanger rupture experimental system and method for a fusion reactor helium-cooled blanket cooling system. The heat exchanger rupture experimental system for a fusion reactor helium-cooled blanket cooling system comprises: a first circuit for conveying helium; a second circuit for conveying water; a simulated rupture pipe, one end of which is connected to the first circuit and the other end of which is connected to the second circuit, and a valve is provided on the simulated rupture pipe; and a steam-water collection device, which is provided on the helium conveying pipe. By providing the heat exchanger rupture experimental system for a fusion reactor helium-cooled blanket cooling system, the effects of a heat exchanger rupture accident on the pressure and temperature of the secondary water circuit, as well as the mechanism and possible effects of secondary water entering the helium circuit through the rupture, can be conveniently studied through simulated tests.

The invention discloses a method for selecting and triggering gamma instant radiation pulse events, and belongs to the technical field of nuclear radiation detection. The method comprises the following steps: carrying out normalization preprocessing on an original gamma pulse radiation time spectrum; s time-frequency transformation is carried out on the preprocessed data, and time-frequency features are extracted; optimizing parameters of the frequency threshold and the amplitude threshold after S time-frequency transformation by adopting a deep reinforcement learning model to obtain an optimal frequency threshold and an optimal amplitude threshold; performing filtering processing on the signal of the S time-frequency conversion result, and separating noise from an effective signal; and searching a pulse radiation event for the filtered signal by applying a morphology-based peak searching method, and positioning the position and the characteristic of a real gamma instant radiation pulse event. According to the method, time-frequency analysis is carried out through S time-frequency transformation, the problem that the frequency of an analysis window cannot be adjusted through short-time window Fourier transformation is solved, the method has better frequency resolution and phase retention characteristics, and gamma pulse signal characteristics can be represented more accurately.

The invention discloses a fast thermal neutron and gamma ray multi-mode detector, and relates to the technical field of nuclear radiation detection, and the detector comprises a detector housing, and the interior of the detector housing is connected with a fast neutron detection unit, a thermal neutron detection unit and a gamma ray detection unit. The gamma ray detection unit is located between the fast neutron detection unit and the thermal neutron detection unit; and an insulating separation unit is connected between two adjacent detection units. The detector can detect fast neutrons, thermal neutrons and gamma rays in the same equipment at the same time, structures such as a cadmium thermal neutron shielding layer and a fast neutron moderation layer do not need to be added, the size of the detector can be greatly reduced, and the detector has the advantages of being compact in structure, stable in performance, wide in energy measurement range, wide in fluence rate measurement range and the like. The ultrahigh-energy high-flux neutron measurement with the neutron energy at least covering # imgabs0 # and the neutron fluence rate at least covering # imgabs1 # can be realized.

The invention provides a beam control system for BNCT treatment. The system comprises a treatment control module, an accelerator control module and a flux monitoring module. The treatment control module is used for acquiring the delivery dose and the delivery time of the BCNT in real time so as to trigger a beam stopping instruction based on the delivery dose or the delivery time, and transmitting the beam stopping instruction to the accelerator control module so as to terminate neutron beam delivery; the accelerator control module is used for receiving a beam stop instruction to correspondingly close the proton beam so as to terminate neutron beam delivery, and automatically close the proton beam when an abnormal condition occurs; the flux monitoring module is used for monitoring neutron flux in real time and transmitting monitoring data to the treatment control module so that the treatment control module can obtain the delivery dosage in real time based on the monitoring data. According to the application, the delivery of the beam is accurately controlled and the delivery dose and the delivery time are monitored in real time in the BNCT treatment process, so that the accuracy and the safety of the beam delivery of the equipment are ensured.

The invention provides an off-site full-range radiation risk evaluation method and system under a severe accident of a nuclear power plant, and the method comprises the steps: S1, building a radioactive accident risk evaluation basic model architecture, adapting to a model demand, and building a corresponding basic database; s2, constructing radioactive smoke plume characteristics after the accident; s3, calculating accident site space gridding and smoke plume transmission discretization; s4, sampling meteorological conditions, and simulating smoke plume transmission; s5, calculating the radiation dose in the early stage of the grid domain, and carrying out risk assessment; s6, performing risk assessment on the health effect in the early stage of the grid domain; s7, calculating the medium-and-long-term stage radiation dose in the grid domain, and performing dose risk assessment; and S8, performing health effect risk assessment and accident consequence assessment in the medium-and-long-term stage. According to the method, the whole transportation process of the radioactive smoke plume under a serious accident is simulated, loss effects such as dry and wet settlement and radioactive decay of the smoke plume are considered, and the activity of the radionuclide deposited on the ground and retained in the air in the off-site space range is determined.

In the case of forming a fine resist pattern, it is desired to further reduce the roughness of the resist pattern.SOLUTION: A substrate processing apparatus comprising: a heat treatment unit configured to bake a resist film; an exposure unit configured to irradiate the resist film having a portion irradiated with a first radioactive ray with a second radioactive ray; a development unit configured to form a resist pattern by development for removing a part of the resist film; and a control unit configured to control the exposure unit such that the second radioactive ray is collectively irradiated to an entire region of the resist film including the portion irradiated with the first radioactive ray and a portion other than the portion irradiated with the first radioactive ray. The first radiation is ionizing radiation or non-ionizing radiation, and the second radiation is non-ionizing radiation. When the first radiation is non-ionizing radiation, the second radiation is non-ionizing radiation having a wavelength longer than the wavelength of the first radiation. The resist film includes a metal oxide photoresist material.SELECTED DRAWING: Figure 1

A radioisotope production capsule is described. Each capsule includes generally an inner container for housing one of a target material and a neutron moderator, an outer container surrounding the inner container for housing the one of the target material and the neutron moderator not housed by the inner container, and cladding for isolating the target material from the neutron moderator. One or more modular capsules are placed in each of a plurality of plug fingers. Each single plug finger loaded with one or more capsules is inserted into a guide thimble of an array of guide thimbles in a fuel assembly.

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

The invention provides a neutron dose evaluation method and system based on mobile phone neutron activation product analysis, and the method comprises the steps: constructing an equivalent medium model for replacing a real mobile phone, and carrying out the neutron energy spectrum solving through the mobile phone activation product. The neutron energy spectrum can be reconstructed on site in daily scenes without professional equipment, such as villages, streets and shopping malls, so that the uncertainty of individual dose is reduced to a level equivalent to that of a laboratory spectrometer, the dependence on a multi-ball spectrometer, a TOF spectrometer and professionals is thoroughly eliminated, rapid and accurate measurement of the neutron energy spectrum and large-scale population dose evaluation are realized, and the accuracy of the neutron energy spectrum is improved. And a basis is provided for delimiting the influence range of the nuclear event, judging the event level of the nuclear event and formulating a hierarchical medical rescue scheme.

The invention relates to the technical field of radiation therapy, in particular to a boron neutron capture therapy beam shaping device and a boron neutron capture therapy system. The beam shaping device for boron neutron capture therapy is used for beam shaping of a DT neutron tube generator. The interior of the beam shaping device is provided with a particle beam channel, and the particle beam channel is used for generating an initial neutron source through an incident proton beam. The beam shaping device comprises a value-added layer, a moderator, a filter layer, a reflecting layer, a collimator and a shielding layer, wherein the value-added layer, the moderator, the filter layer and the collimator are sequentially arranged from a target material to an outlet. And the axes of the particle beam channel, the value-added layer, the moderator and the collimator coincide. According to the beam shaping device, 14Mev high-energy neutrons from the DT neutron tube generator are shaped into hot / slow neutron beams meeting the BNCT treatment requirements, and impurities of fast neutrons and gamma rays are reduced to the maximum extent, so that the dosage precision and biological selectivity of treatment are effectively improved.

The utility model relates to a nuclear power high-radiation object containing device and containing and transferring equipment. The containing and transferring equipment comprises the nuclear power high-radiation object containing device. The nuclear power high-radioactivity storage device is specially designed for underwater operation, and can safely store and seal high-radioactivity waste under the condition that normal operation of a reactor is not affected. The sealing mechanism ensures that the radioactive substance storage space is completely sealed in the transferring and long-time storage process, radioactive substances are prevented from leaking, and the safety of the treatment process is greatly improved. And secondly, the torque input end allows torque to be input through an external tool to achieve rotation of the lock cylinder, so that the closing or opening action is rapidly and effectively completed, the operation process of containing and closing the radioactive substances is simplified, and the containing and closing efficiency of the radioactive wastes is improved.

The invention relates to the technical field of radiation monitoring, in particular to a radioactive foam height nuclear monitoring system and a use method. A radioactive foam height nuclear monitoring system comprises an ionization chamber detector; the collimation shielding module is provided with a containing space, the ionization chamber detector is contained in the containing space, the collimation shielding module is provided with a collimation hole, and particles generated by the self-radiation source can pass through the collimation hole. The invention provides a radioactive foam height nuclear monitoring system and a use method, and aims to solve the problem that a conventional radiation detector is difficult to bear an extremely high radiation environment and affects the detection precision.

The invention relates to a device and a method for measuring concrete volume change caused by long-term neutron irradiation, the device comprises a neutron emitter and a neutron receiver which are arranged in a laboratory in a matching manner, a test concrete test piece is fixed between the neutron emitter and the neutron receiver, and the test concrete test piece measures the temperature through a temperature detector; a contrast concrete test piece is arranged in the test chamber, a collection mold wraps the outer side of the contrast concrete test piece, and a condensation pipe, a water vapor collector and a high-precision electronic scale are arranged. The method comprises the following steps: 1, measuring the overall expansion rate of a concrete test piece through a strain measurer; 2, testing the volume change of the concrete test piece in the environment; 3, calculating the volume change rate of the concrete caused by neutron radiation by combining the thermal expansion coefficient of the concrete and the drying shrinkage of the concrete; and 4, the relationship between the volume expansion rate of the concrete and the neutron irradiation dose is tested, and the relationship between the volume change rate of the shielding concrete of the engineering structure and the time is speculated, so that the safety of the nuclear engineering structure is ensured.

The invention discloses a gas target device for isotope production, and the gas target device comprises a seat body which is provided with a channel; the water-cooled jacket body is mounted on the seat body, and the water-cooled jacket body is provided with a water-cooled cavity for circulating a water-cooled medium; the target body is installed on the base body and comprises a target body, the target body is located in the water cooling cavity and is provided with a target cavity, and the target cavity, the channel and the accelerator beam leading-out port are sequentially arranged in the set direction. According to the gas target device for isotope production disclosed by the embodiment of the invention, the water-cooled jacket body is arranged for cooling the target body, so that the target body is prevented from being damaged due to overhigh temperature of the target gas, the target gas can receive beam irradiation with higher flow intensity, and the isotope yield is improved.

The invention relates to the technical field of nuclear fusion, and discloses a vacuum chamber cold shield module and a vacuum chamber cold shield for a nuclear fusion device.The vacuum chamber cold shield module comprises two panel assemblies and a cooling assembly, the two panel assemblies are arranged in the polar direction, and each panel assembly comprises an inner side panel assembly and an outer side panel assembly; the inner side panel and the outer side panel assembly surround a circle in the annular direction, the outer side panel assembly comprises a first outer side panel and a second outer side panel which are arranged in the polar direction, each panel assembly is correspondingly provided with two cooling assemblies, one cooling assembly surrounds the periphery of the first outer side panel and the periphery of the inner side panel in the annular direction, and the other cooling assembly surrounds the periphery of the second outer side panel in the polar direction. The other cooling assembly surrounds the periphery of the second outer side panel and the periphery of the inner side panel in the annular direction, each cooling assembly comprises a plurality of cooling pipelines, the cooling pipelines are arranged at intervals in the polar direction, and the cooling pipelines are filled with cooling media. The vacuum chamber cold shield module for the nuclear fusion device is convenient to mount, high in heat shielding efficiency and uniform in heat transfer performance.

The invention provides a measurement system for the waviness of a neutron conduit. The measurement system comprises a high-precision granite guide rail, a total station, an auto-collimation eyepiece, a computer and a measurement auxiliary assembly. The high-precision granite guide rail provides a stable sliding reference, the total station slides along the high-precision granite guide rail for measurement, the auto-collimation eyepiece is matched with the normal direction of the measurement conduit, and the computer processes data. The system can adapt to measurement requirements of neutron conduits in different geometrical shapes, and the waviness is calculated through a preset formula, and the assembly precision of multiple sections of conduits and the influence on neutron reflection are evaluated; the measurement auxiliary assembly and the jack ensure stable measurement. The system is high in measurement precision, strong in universality, efficient in data processing, good in stability, simple and convenient to operate and capable of guiding design and manufacturing of neutron conduits, reducing production cost and improving neutron flux and experiment accuracy and reliability.