3480 results about "Pressure vessel" patented technology

The invention provides an intelligent material damage diagnosis method and system based on magnetic characteristic data fusion, and relates to the technical field of nondestructive testing, and the method comprises the following steps: collecting magnetic characteristic data by using a magnetic stress detection robot; performing multi-scale decomposition on the data to construct a magnetic domain evolution characteristic spectrum; inputting the characteristic spectrum into a composite neural network to extract a material damage characteristic matrix; constructing a fusion feature vector by using tensor dimensionality reduction and a multilayer belief transfer network; and realizing damage calculation through temperature field modulation and self-adaptive weight distribution to obtain the damage grade and the residual life. According to the invention, accurate diagnosis of the material damage in the welding seam area of the pressure vessel is realized.

The invention provides a multi-mode ultrasonic fusion pressure vessel weld defect nondestructive testing method and system, and relates to the technical field of nondestructive testing. According to the method, geometric parameters of a welding seam are obtained through three-dimensional laser scanning, and an optimal scanning parameter set is generated; driving ultrasonic phased array equipment to scan for one time and synchronously acquire shear wave full-matrix capture and longitudinal wave linear scanning data; performing energy flow angular spectrum analysis and envelope analysis on the bimodal data, extracting defect feature parameters and constructing a three-dimensional feature tensor; carrying out multi-dimensional feature fusion by adopting Tucker decomposition, and enhancing a core tensor through physical modeling; generating three types of defect indication diagrams including a defect existence possibility diagram, a defect relative scale diagram and a defect space orientation diagram from the enhanced feature tensor; and the three types of indication diagrams are visually presented for comprehensive interpretation of detection personnel. Through multi-modal data fusion and physical modeling enhancement, the defect identification accuracy and detection efficiency are remarkably improved, the false alarm rate is reduced, and reliable technical support is provided for pressure vessel welding seam safety detection.

The invention provides welding seam nondestructive testing equipment and method for a high-precision pressure vessel, and relates to the technical field of welding seam detection, the welding seam nondestructive testing equipment comprises a flaw detector main body, a data line, a probe and a fixed ring, two ends of the data line are respectively connected with the flaw detector main body and the probe, a movable frame is slidably mounted on one side of the fixed ring, and an adjustable track is mounted on the fixed ring. According to the nondestructive testing equipment and method for the welding seam of the high-precision pressure container, through the arrangement of the flaw detector main body, the data line, the probe, the fixed ring, the movable frame, the movable frame, the mounting frame, the adjustable track and the buffer structure, the wavelength of the adjustable track can be adjusted according to the width of the welding seam on the pressure container, so that the welding seam area is better covered, and the welding seam detection accuracy is improved. The device is simple and convenient to operate, in addition, it can be ensured that the probe can be better attached to a weld joint to conduct scanning operation, in the scanning process, the effect of buffering and protecting the external force borne by the probe can be well achieved, and damage to the probe is reduced.

One variation of a system includes a pressure vessel: including a wall; defining a primary working fluid circuit extending vertically within the wall; defining a secondary working fluid circuit extending vertically within the wall and fluidly isolated from the primary working fluid circuit; and configured to store a nuclear fuel, a primary working fluid, and a secondary working fluid. The wall of the pressure vessel: defines a heat exchanger configured to transfer thermal energy from the primary working fluid flowing through the primary working fluid circuit into the secondary working fluid flowing through the secondary working fluid circuit; and defines a radiation shield configured to attenuate radiation emitted by the nuclear fuel.

An ultra-deep carbonate rock dissolution simulation experiment device and method. The experiment device comprises: at least two reaction kettles (1) arranged in series connection, the reaction kettles (1) each comprising a confining pressure mechanism (10) and an axial pressure mechanism (20), wherein the confining pressure mechanism (10) is provided with a rock core cavity for accommodating a rock core (2) and can apply confining pressure to the rock core (2), the axial pressure mechanism (20) is used for applying axial pressure to the rock core (2) in the rock core cavity, and the axial pressure mechanism (20) is provided with a reaction solution interface communicating with the rock core cavity; a solution pressure vessel system (40), capable of providing a reaction solution and injecting the reaction solution into the rock core cavities by means of the reaction solution interfaces; at least two back pressure control devices (30), outlet ends of the rock core cavities of the reaction kettles (1) being connected to the back pressure control devices (30); and a detection system (50). The rock core cavities of the reaction kettles (1) are in series connection, and the reaction solution provided by the solution pressure vessel system (40) can sequentially flow through the rock core cavities in series connection, and the detection system (50) is used for separately performing detection on each rock core cavity, thereby solving the technical problem of the difficulty in conducting simulation experiments with respect to the dissolution of strongly altered carbonate rocks in ten-thousand-meter ultra-deep conditions.

A drive system for a vehicle includes a frame, an electric motor, and an energy storage unit suspended from the frame of the vehicle. The energy storage unit includes at least two energy modules including a first energy module having a first cuboid fuel tank and a first cuboid energy storage device including at least one battery. The at least two energy modules further include a second energy module having a second cuboid fuel tank. The at least two energy modules are connected to each other such that the first cuboid fuel tank and the second cuboid fuel tank are connected to opposite sides of the first cuboid energy storage device.

The invention discloses internal and external galvanization equipment for a special pressure vessel, and belongs to the technical field of pressure vessel galvanization, the internal and external galvanization equipment for the special pressure vessel comprises a placing mechanism for galvanization of the pressure vessel, the placing mechanism comprises a bottom plate and a lifting frame, and six connecting rods are fixedly mounted on the lifting frame; each connecting rod is provided with two taking and placing mechanisms used for clamping the pressure container to be galvanized. According to the invention, through the arrangement of the multi-station synchronous operation putting-in mechanism, the automatic lifting, translation and descending of the pressure container are realized, so that the galvanizing, unloading and loading processes are continuously carried out, and the production efficiency is greatly improved; according to the pick-and-place mechanism, through alternate driving of a driving triangular wheel and a driven triangular wheel, supporting points of a clamping rod are switched in a staged mode in the galvanization process, it is guaranteed that connecting lugs of a pressure container are not fixedly shielded, and galvanization blind areas are avoided; through cooperation of the compression spring and the lower friction ring, the passive triangular wheel is kept fixed in a non-driving state, and accidental rotation is prevented.

An evaporator can include a pressure vessel and an evaporation device. The evaporation device can be at least partially enclosed within the pressure vessel and configured to direct a refrigerant through the pressure vessel. The evaporator can include at least one fluid direction device at least partially enclosed within the pressure vessel. The at least one fluid direction device is configured to direct a drinking fluid around the evaporation device to facilitate heat exchange. The evaporation device can include an evaporation coil with a first portion, a second portion, and a third portion. The second portion can be located exterior to the first portion and the third portion can be located radially exterior to the second portion. The pressure vessel can include an inlet and outlet in fluid connection with the evaporation coil.

An underdrain filtered water collection system includes: a pair of opposing drainpipes, each drainpipe having a plurality of collection drains; and a diffuser screen. The diffuser screen can slide within an outlet in each of the collection drains. A diffuser screen for a pressure vessel containing filter media includes: a screen pipe; a solid plate coupled to a base of the screen pipe; and a winged diffuser arranged around an outer circumference of the solid plate. The winged diffuser includes a plurality of foldable wings. The screen pipe includes a mesh screen having preconfigured interstices therethrough. Feed water flows through the screen pipe where it is directed by an inner surface of the solid plate to flow in a diffused flow through the interstices of the mesh screen and the wings.

The present application discloses a method and system for identifying internal surface defects of a nuclear reactor pressure vessel, a computer device, and a computer-readable storage medium. The method comprises: collecting image data of the surface of a pressure vessel; constructing an illumination angle attention mechanism, using an image in a data set to establish a feature map, and producing a spatial attention map on the basis of a spatial relationship of the feature map; and using the illumination angle attention mechanism to improve a YOLOv5 model, and identifying surface defects of the pressure vessel by means of the improved YOLOv5. The present application has the characteristics of high defect identification efficiency, low missed detection rate, etc. The present application can effectively cope with common problems when defect detection is performed under different illumination conditions. This precise defect localization and identification capability is critical for ensuring safe operation of pressure vessels, particularly during routine maintenance and inspection.

The invention relates to the technical field of intelligent diagnosis, in particular to a pressure vessel health monitoring method based on an intelligent algorithm, which comprises the following steps: acquiring pressure, stress and temperature data in real time by using a sensor array, calculating a track evolution parameter set, identifying a damaged area, detecting a fault event, and predicting a health state and residual service life. And establishing a damage grade classification framework, and obtaining a damage grade classification result. According to the method, through multi-source data real-time acquisition and spatial gradient refining processing, by using a pressure and stress distribution coupling relation, accurate damage positioning is realized, the anomaly detection sensitivity is improved, damage boundary coordinates are marked, the expansion rate of adjacent damage areas is quantified, and phase delay is judged in combination with a multi-period pressure track; fault recognition stability is enhanced, abnormal event classification precision is optimized, a material fatigue accumulation and pressure uniformity correlation means is adopted, health score attenuation observation is enhanced, health state quantification depth is improved, and life prediction reliability is expanded.

The invention provides a repairing method and a repairing system for sealing surface defects of a nuclear reactor pressure vessel, and belongs to the technical field of nuclear power maintenance. The repairing method comprises the following steps: performing defect detection on the sealing surface of the pressure vessel; performing polishing repair or welding repair by adopting a corresponding repair method according to the distribution mode, type and size of the defects, wherein the welding repair process and process parameters are determined according to the thickness of the residual anticorrosive coating at the bottom of the welding groove after the defects are removed, the finite element simulation welding temperature field and the welding effect evaluation on the test piece; and after welding, the welding repair part is ground, so that the welding repair area meets the requirements of flatness and roughness. The repairing efficiency is greatly improved, the repairing effect is guaranteed, the personnel radiation time is shortened, and the service life of the sealing surface of the pressure vessel is prolonged.

The invention discloses a reactor pressure vessel fatigue analysis method in a marine environment, which belongs to the technical field of pressure vessel analysis, and comprises the following steps: calculating a transfer function of a structure under the action of a wave load through a spectrum analysis method, and obtaining a stress component power spectrum density function of a node based on a sea condition parameter; converting the frequency domain signal into a time domain signal; calculating a stress time history under the action of the thermal-internal pressure load and carrying out superposition of stress component time histories to obtain a fatigue stress value of the structure; and calculating the fatigue damage value of each stress cycle, obtaining the fatigue damage of each group of time history, and obtaining the total fatigue damage under the working condition. According to the method, the defects of the existing fatigue analysis method can be overcome, and the fatigue damage of the reactor pressure vessel of the nuclear power station under the combined action of multiple loads in heat, internal pressure and marine environment can be accurately evaluated.

The invention discloses an in-situ global foreign matter checking and grabbing system for reactor internals on the lower portion of a reactor. The in-situ global foreign matter checking and grabbing system for the reactor internals on the lower portion of the reactor comprises a base device, an adjusting device and a foreign matter grabbing device. The foreign matter grabbing device is arranged on the base device through the adjusting device. The foreign matter grabbing device comprises a flexible arm assembly, a flexible arm driving assembly, a quick change assembly, at least one clamping jaw used for grabbing foreign matter and a video tracking and checking assembly used for searching the foreign matter and monitoring the grabbing condition. The flexible arm assembly is arranged on the adjusting device; the at least one clamping jaw is detachably arranged on the flexible arm assembly through the quick-change assembly; the video tracking and checking assembly is arranged on the adjusting device; according to the invention, the flexible arm assembly carries various types of clamping jaws to carry out automatic grabbing operation, so that the in-service nuclear power plant reactor internals can accurately, efficiently and safely grab and clean foreign matters in the in-situ interior of a pressure vessel in a whole region.

The bevel groove edge milling device suitable for auxiliary welding of the LNG pressure container solves the problems that the workload of double-face edge milling is large, edge milling movement guiding cannot be achieved, edge milling is prone to shifting, and the edge milling accuracy is poor, the bevel groove edge milling device comprises an edge milling rack and a mounting rack, and a second mounting rack and a first mounting rack are fixedly mounted on the inner side of the mounting rack; an upper clamping plate is welded to one side of the mounting frame, a positioning frame is welded to the inner side of the upper clamping plate, a driving set and a driven shaft are movably mounted on the inner side of the positioning frame, a transmission frame is slidably connected to the inner side of the positioning frame, a first driving bevel gear rotates in the transmission frame, and first driven bevel gears are arranged on the surfaces of the driven shaft and the driving set; a universal joint is arranged between the two first driving bevel gears, and a milling cutter is installed at one end of the driving set and one end of the driven shaft, the milling cutter connected with one end of the driving set is driven to rotate through conventional driving work of the driving set, and meanwhile when the driving set is driven to work, the milling cutter is driven to rotate. And the first driving bevel gear and the first driven bevel gear which are matched with the driving set can be driven to rotate in a meshed mode.

The invention provides a free boundary supporting system for a horizontal modal test of a large rocket. The free boundary supporting system at least comprises a rack car, a pressure container, a free membrane type air spring and a control assembly. The rack car at least comprises a bottom truss and a top truss, and the bottom truss is provided with a moving device; the pressure container is specifically a gas storage container located between the bottom truss and the top truss, and the top of the pressure container is provided with a sealing flange connector. The free membrane type air spring is arranged on the upper end face of the top truss, the bottom of the free membrane type air spring communicates with the pressure container through the sealing flange connector, and a bracket used for supporting a rocket is arranged on the top of the free membrane type air spring. The control assembly at least comprises an acquisition module, a controller and an execution module which are in communication connection in sequence; freedom degrees of translation, rotation and torsion of the rocket in a modal test are provided by the free membrane type air spring.

The invention discloses a manufacturing method of a high-efficiency and low-cost steel plate for a 345MPa-grade low-temperature pressure vessel, and belongs to the technical field of low-carbon microalloyed steel production. The manufacturing method comprises the steps of molten steel smelting, LF refining, RH vacuum degassing, continuous casting, casting blank heating, rolling, controlled cooling and straightening. The problems that steel plate rolling efficiency is low, rolling resistance is large, and the plate shape is not easy to control are solved, the steel plate is low in cost, high in strength and toughness and high in straightness, and the service safety of the steel plate for the low-temperature pressure container can be guaranteed.

Disclosed herein is an aircraft with engines positioned so as to avoid damage to other components of the aircraft. The aircraft may include a blended wing body aircraft. The engines may be positioned aft of a pressure vessel of the aircraft. The engines may be positioned aft of and / or above a fuel store of the aircraft. Such engine positioning may reduce the likelihood of damage to a pressure vessel and / or fuel store in the event of engine failure.

The invention discloses a pressure vessel inner circular seam welding device and an inner circular seam welding method, and relates to the technical field of pressure vessel inner circular seam welding. The pressure vessel inner girth welding device comprises a left fixing table and a right fixing table which are used for preliminarily fixing a pressure vessel shell. And the annular clamping unit comprises an outer clamping assembly and an inner clamping assembly, and the outer clamping assembly and the inner clamping assembly can apply opposite clamping force in the radial direction to the shell from the inner side and the outer side of the shell correspondingly. By arranging the connecting structure, the welding unit can drive the annular clamping unit to synchronously act in the process of entering the shell and aligning to a welding seam, so that efficient cooperation of clamping and welding operation is realized; the annular clamping unit synchronously applies clamping force which is close to each other in the radial direction of the shell from the inner side and the outer side of the shell through the outer clamping assembly and the inner clamping assembly, and therefore bidirectional stable clamping of the end of the shell is achieved.

The invention discloses a passive nuclear steam supply system which is characterized in that two ends of a hot-section main pipeline are respectively connected with a reactor pressure vessel and a steam generator, a main pump is vertically connected with the steam generator, two ends of a cold-section main pipeline are respectively connected with the pressure vessel and the main pump, the hot-section main pipeline is provided with a first liquid level pressure tap and a second liquid level pressure tap, and the cold-section main pipeline is provided with a second liquid level pressure tap. The first liquid level pressure tap is located at the bottom of the hot section main pipeline, the second liquid level pressure tap is close to the steam generator and located at the top of the hot section main pipeline, the reactor coolant system further comprises a pressure stabilizer and a surge pipe, one end of the surge pipe is connected to one of the hot section main pipelines, and the other end of the surge pipe is connected to the bottom of the pressure stabilizer. The passive nuclear steam supply system can allow the rated power of the reactor core to be remarkably improved.

The invention relates to the technical field of safety monitoring of a nuclear reactor, and particularly discloses a multi-region pressure overrun leakage monitoring method for a reactor pressure vessel. The method comprises the steps of multi-region pressure data acquisition, real-time pressure field model construction, dynamic pressure field baseline modeling, pressure overrun anomaly detection, leakage source accurate positioning and evaluation based on spatial gradient analysis, topological structure mapping and multi-sensor data fusion, and graded early warning and response. By the adoption of the technical scheme, real-time and fine monitoring of pressure distribution in the reactor pressure vessel can be achieved, the rapid and accurate judgment and positioning capacity of leakage events is improved, the operation safety and reliability of nuclear power facilities are enhanced, and the reliability of the nuclear power facilities is improved. The defects of independent monitoring, local accurate positioning and complex working condition adaptability of multi-region pressure over-limit leakage in the prior art are overcome.

The invention discloses a safety interlocking testing device for a quick-opening pressure vessel, which is characterized by comprising a first pipeline system, a second pipeline system and an electrical control system, the first pipeline system and the second pipeline system are both connected with the electrical control system; the first pipeline system comprises a first pipeline body and a first pressure sensor; the second pipeline system comprises a second pipeline body and a second pressure sensor; when a functional test is carried out on the safety interlocking device under the condition that a door or a cover of the quick-opening-door pressure container is not closed in place, the first pipeline system and the second pipeline system are connected with a third electromagnetic valve of the quick-opening-door pressure container. Whether the safety interlocking function is normal or not is judged by judging readings of the first pressure sensor and the second pressure sensor; when functional testing is carried out on the safety interlocking device under the condition that internal pressure of the quick-opening pressure container is not completely released, the first pipeline system is connected with a pressure gauge of the quick-opening pressure container, the under-pressure working condition of the quick-opening pressure container is simulated, and whether the safety interlocking function is normal or not is judged according to whether a door or a cover of the quick-opening pressure container is opened or not. The beneficial effects of the invention are that the system can safely and rapidly carry out the functional testing of the safety interlocking device, and is effective, safe, energy-saving and applicable.

The invention provides a pressure vessel full life cycle stress fatigue assessment and predictive maintenance system based on digital twinning. The system comprises a model construction module used for constructing a three-dimensional digital twinning model corresponding to a solid pressure vessel; the data synchronization module is used for integrating historical test data and actual operation load data of the solid pressure vessel into the three-dimensional digital twinborn model and simulating dynamic stress distribution of the solid pressure vessel in an actual operation load process; the evaluation and maintenance module is used for evaluating the accumulated fatigue damage of the solid pressure vessel and the residual fatigue life in the current state based on the dynamic stress distribution, and determining a potential risk area and a risk time window of the solid pressure vessel based on an evaluation result; and on-demand inspection plans and predictive maintenance strategies of the entity pressure vessels are generated based on the potential risk areas and the risk time windows. Stress fatigue evaluation of the whole life cycle is achieved, and the accuracy and reliability of life prediction are remarkably improved.

The invention discloses a detection alarm method and system for detecting surface defects of a pressure vessel, and relates to the field of surface defects of the pressure vessel, and the method comprises the following steps: obtaining sound wave reflection information of the surface of the pressure vessel, and identifying a defect area existing on the surface of the pressure vessel based on the sound wave reflection information; judging the characteristic state of the surface defect of the pressure vessel by combining the sound wave reflection intensity; combining the characteristic state with a stress elastic-plastic analysis technology to obtain damage modes of different position points in the surface defect area of the pressure vessel, and determining a damage characterization parameter and a damage evolution rule according to the damage modes; and according to the damage characterization parameter and the damage evolution law, evaluating a risk value of leakage of the pressure vessel, generating an alarm prompt based on the risk value, and sending the alarm prompt to a management terminal to perform pressure vessel risk management and control. According to the method, the damage state of the container can be accurately described, the future performance degradation of the container can be predicted, and early warning is facilitated.

A welding device for a chemical pressure vessel comprises a mounting box body, an adjusting and supporting device, a synchronous driving device and follow-up clamping devices, the adjusting and supporting device is arranged on the mounting box body in a sliding mode, the synchronous driving device is fixedly arranged on the mounting box body and used for synchronous rotation driving of a barrel to be tailor-welded, the number of the follow-up clamping devices is two, and the adjusting and supporting device is arranged on the mounting box body. The two groups of follow-up clamping devices are the same in structure, the two groups of follow-up clamping devices are rotationally arranged on the mounting box body respectively and are used for clamping and positioning a barrel, any group of follow-up clamping device comprises a sliding block and a clamping plate, the sliding block is used for controlling conversion of clamping action and rotating action, and the clamping plate is used for clamping and positioning the barrel. The synchronous driving device can synchronously transmit driving force to the two sets of follow-up clamping devices, so that the two sets of follow-up clamping devices drive the clamped barrel to rotate synchronously, the barrel is prevented from moving relatively, the spot welding fixing procedure can be omitted, and the machining efficiency is improved.

A fuel rail and a method for producing the fuel rail for a pressure vessel system are provided. The method provides a fuel line and configures a plurality of rail connectors. The rail connectors have a cross-sectional area that is enlarged in comparison to the provided fuel line, and the rail connectors are configured so as to be integral to the fuel line.

The invention relates to the technical field of pressure vessel main body welding, in particular to an alignment welding assembly for quickly welding a boiler barrel of an industrial boiler container, which comprises a first driving support piece, a second driving support piece is fixedly arranged on one side of the first driving support piece, and a left position control unit is fixedly arranged on a connecting seat on the left side of the first driving support piece; and a left position control unit is fixedly installed on the ground connecting base on the right side of the second driving supporting piece, a right position control unit is fixedly installed on the ground connecting base on the right side of the second driving supporting piece, a steel rope set is arranged between the left position control unit and the right position control unit, an inner welding assembly is installed in an inner barrel cavity of the boiler barrel, and an outer welding assembly is installed below the boiler barrel. According to the device, the left position control unit and the right position control unit are adopted to drive the steel rope set to rotate, the outer welding assembly is driven to quickly shift and weld along the longitudinal seam of the boiler barrel, and meanwhile, the inner welding assembly and the outer welding assembly can synchronously work to synchronously weld the inner and outer longitudinal seams of the boiler barrel; when the annular butt joint seam is welded, the boiler barrel and the pipe base synchronously rotate to be matched with the outer welding assembly and the inner welding mechanism, and rapid welding is achieved.

The invention relates to a pressure vessel (1), comprising a vessel body (3), wherein at an upper end of the vessel body (3) an end region (2) is formed in one piece with the vessel body (3), which has an opening (O), and a fastening structure (9) for a valve (6) formed on the inside of a wall (2.1) surrounding the opening (O) of the end region (2). According to the invention, two outflow openings (SO) are formed opposite each other in the wall (2.1) surrounding the opening (O) of the end region (2).

The utility model relates to the technical field of sensors, in particular to a sensor with high pressure resistance. The sensor with the high pressure resistance comprises a shell and a core body, the shell is provided with a first mounting port and a second mounting port which are communicated with the interior of the shell, the first mounting port is used for being communicated with an outlet of a pressure container, the second mounting port is used for mounting the core body, and the first mounting port and the second mounting port are located at the two axial opposite ends of the shell respectively; wherein the inner wall of the shell is provided with an inner surface, the outer wall of the core body is provided with an outer surface, and the inner surface and the outer surface are in interference fit in a mounting state. According to the scheme, the problem that the core body is damaged due to the fact that the welding temperature is too high can be avoided, and the problem that the connecting strength of the shell and the core body is limited due to the size of a welding point can also be avoided.

The utility model discloses a high-pressure-difference submarine cable cabin-penetrating sealing structure for testing a wet-type electric connector, which belongs to the technical field of submarine cable cabin-penetrating sealing and comprises a pressure vessel cabin wall, a cabin wall flange is arranged in the pressure vessel cabin wall, a screw is arranged on the surface of the cabin wall flange, a submarine cable body is arranged in the cabin wall flange, and the submarine cable body is connected with the cabin wall flange. V-group compression nuts are arranged at the two ends of the bulkhead flange, a V-group pressure pad is arranged in the bulkhead flange corresponding to the submarine cable body, and a V-group support ring is arranged on one side of the V-group pressure pad; according to the utility model, the V-group pressure pads, the V-group support rings, the V-shaped seals and the V-group pressure rings are tightly attached to the submarine cable, so that high-pressure-difference sealing is realized, the combination direction of the V-group seals can be determined according to the water pressure direction, and the high pressure difference is realized by adjusting the number of single V-shaped seals through different pressure differences; the problem of unsafe factors in the test of the cabin-penetrating sealing structure which cannot bear high pressure difference in the prior art is solved, and the test operation risk is reduced.