5445 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.

Assemblies and method to extract a material from a material source may include a vacuum and material collector assembly to enhance extraction of the material from the material source. The vacuum and material collector assembly may include a material collector comprising a high volume pressure vessel having an interior and a high-pressure vacuum source pneumatically coupled to the pressure vessel. The vacuum source is operable to generate a high-pressure vacuum of a fluid flow through the interior of the pressure vessel to extract the waste material from the waste material source into the interior of the pressure vessel. The vacuum source may be connected to the pressure vessel of the material collector to form a unified vacuum and material collector assembly which may be supported on a single mobile chassis.

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.

The utility model discloses assembly welding equipment for a flange connecting pipe of a pressure vessel, which belongs to the technical field of pressure vessel manufacturing equipment and comprises a first workpiece clamping component fixedly arranged on a lathe bed and a second workpiece clamping component arranged on the lathe bed through a moving component, and the second workpiece clamping component can be close to or far away from the first workpiece clamping component. The first workpiece clamping assembly and the second workpiece clamping assembly each comprise a chuck fixing base, and a rotating chuck is installed on one side of each chuck fixing base. Three clamping jaws are arranged on the rotary chuck; the clamping jaws can move in the radial direction of the rotary chuck. The clamping jaw is driven by a first pneumatic motor; the rotary chucks are driven by a second pneumatic motor to rotate, and the center lines of the two rotary chucks are coaxial; the device further comprises a welding mechanism and a ground wire contact block. The welding mechanism is arranged corresponding to a welded junction of the flange and the connecting pipe. The ground wire contact block is arranged on a chuck fixing seat of the first workpiece clamping assembly; according to the utility model, the assembly precision can be improved, the clamping time can be shortened, and the processing efficiency can be improved.

The invention discloses an intelligent auxiliary system and method for regular inspection of a pressure vessel, and aims to improve the intelligence, efficiency and accuracy of inspection of the pressure vessel. The system comprises a data acquisition module, a data processing module, a risk assessment module, an inspection plan generation module, a report generation module, a remote monitoring module and a historical data management module. Operation parameters of the pressure vessel are collected in real time through the sensor, the data processing module carries out elimination and trend analysis on abnormal data, and the risk assessment module assesses the operation state of the pressure vessel through machine learning and a fuzzy logic algorithm. The system dynamically generates an inspection plan according to an evaluation result and adjusts an inspection period through Bayesian updating, and a generated inspection report has a digital signature to ensure safety. The historical data management module stores and analyzes long-term data and supports trend prediction of equipment health conditions, and the remote monitoring module provides real-time state checking and early warning.

The invention relates to the technical field of monitoring and early warning, in particular to an intelligent pressure vessel pressure monitoring and early warning system which comprises an environmental influence assessment module, a pressure state analysis module, a pressure trend analysis module and a risk assessment and early warning module. According to the invention, by analyzing the correlation between the environment temperature and the service life of the pressure vessel, the early warning threshold value is automatically adjusted, the dynamic adaptability of the early warning threshold value is realized, the real condition of the pressure vessel in a specific operation environment is reflected more accurately, the accuracy and timeliness of safety early warning are improved, and the working efficiency is improved. By means of calculation of the pressure state deviation index and the deviation state grade, the safety state of the pressure container can be judged more accurately, potential risks are evaluated more pertinently, the abnormal pressure change trend can be recognized through continuous analysis of the pressure change rate, the service life condition of the pressure container is combined, and the safety of the pressure container is improved. And the overall abnormal risk is evaluated and the corresponding early warning level is formulated, so that the potential safety accident risk is reduced.

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.

High pressure compressed gas pressure vessels and devices utilizing such vessels are disclosed herein. More particularly, aspects of the present invention are directed to high pressure (i.e., nitrogen or N2 based) pressurized gas cylinders with pierceable membranes recessed from the opening of the pressure vessel such that prior art piercing mechanisms cannot pierce the membrane for safety purposes. Additionally, aspects of the present invention are directed to pressurized gas operated devices with elongated pins for piercing pressure vessels with recessed pierceable membranes.

The invention discloses girth welding equipment for pressure vessel production, belongs to the technical field of welding, and aims to solve the problems that the overall production efficiency of welding is low, and the health of operators can be threatened when flue gas is directly discharged into a working environment. A welding device is arranged on the rack, a guide rod is fixedly connected into the rack below the welding device, a servo motor and a first belt are fixedly connected to the bottom end of the rack below the guide rod, the first belt is arranged on the outer side of the extending end of the servo motor in a sleeving mode, a rotating shaft is arranged in the first belt, and a driving gear is arranged on the outer side of the rotating shaft in a sleeving mode. By means of the device, left-right alternate feeding can be achieved, the waiting time is shortened, the welding process is more continuous and efficient, meanwhile, smoke generated during welding can be collected, emission of harmful gas and smoke dust is reduced, and air pollution of a welding area is reduced.

The invention relates to the technical field of pressure vessel machining, solves the technical problems that in the polishing process, a pressure vessel cannot be well fixed, consequently, the pressure vessel is prone to shaking, and the polishing effect on a welding seam is affected, and particularly relates to an automatic polishing device for the welding seam of the pressure vessel. Comprising a bottom plate and a pressure vessel main body needing to be subjected to weld joint polishing, a fixing mechanism used for fixing the pressure vessel main body is arranged on the bottom plate, two clamping plates can be driven to move towards the middle position to clamp the pressure vessel main body through the arranged clamping mechanism, meanwhile, a plurality of semi-cylindrical rubber cushions are arranged on the clamping plates, and the pressure vessel main body is clamped through the rubber cushions. In the moving process of the clamping plates, the rubber cushions can make contact with the surface of the pressure container body and deform, so that the rubber cushions are better attached to the surface of the pressure container body, the friction force is further increased, the two ends of the pressure container body are fixed, and the pressure container body cannot move or rotate; and subsequent grinding is more convenient.

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.

Disclosed is a nuclear reactor, comprising: a canister, a nuclear reactor core housed inside of the canister, and a controlled temperature housing attached to the canister. The nuclear reactor core comprises a control drum and a shaft extending from the control drum and out of the nuclear reactor core. Heat generated by the nuclear reactor core enters the controlled temperature housing. The controlled temperature housing comprises a proximal end attached to the canister, a first internal plate spaced from and positioned distal to the proximal end, a second internal plate spaced from and positioned distal to the first internal plate, and a motor mounted to the second internal plate. The shaft enters the controlled temperature housing through the proximal end and extends to the motor. The controlled temperature housing is to passively maintain the motor at a temperature equal to or below a predetermined temperature threshold.

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.

A pressure vessel is provided that has a structural shell formed by winding filaments upon a substantially cylindrical form. The structural shell has a first filament and a second filament. The first filament includes of a first material. The first filament is wound about the form in a primarily hoop direction. The second filament includes a second material. The second material is different from the first material. The second filament is wound about the form in a primarily helical direction. The first filament and second filament are interwoven in a layer upon the form.

The invention discloses an intelligent welding process evaluation optimization system based on an artificial intelligence big language model, and aims to improve the screening and optimization efficiency of a welding process evaluation report. According to the system, a natural language processing technology is used for analyzing welding requirements input by a user, relevant parameters are automatically extracted from a welding process evaluation report database, and evaluation reports are intelligently sorted and screened through a multi-dimensional data analysis module. The system generates optimized welding process suggestions according to multiple factors such as welding materials, process parameters and structural complexity. Meanwhile, the system has a self-adaptive learning function, process optimization adjustment can be carried out based on historical data and simulation results, and continuous improvement of the recommended process is ensured. The system can also be integrated with welding simulation tools (such as ANSYS and SYSWELD), the feasibility of a recommended process is verified, and the system is suitable for welding process selection and optimization of key structures such as pressure containers and pipelines in complex welding projects. According to the method, the efficiency, accuracy and reliability of welding process evaluation are remarkably improved, and the method has wide industrial application prospects.

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 invention discloses a submerged-arc welding external welding device for a pressure vessel and an external welding method of the submerged-arc welding external welding device, and belongs to the technical field of submerged-arc welding external welding. Comprising a supporting base; submerged-arc welding equipment is arranged on the side surface of the supporting base; the turnover support is movably arranged on one side of the supporting base; a rotating ring is rotationally connected into the overturning support. A rotating cylinder is movably connected into the rotating ring; a thread clamping assembly is arranged on the rotating cylinder body; the movable support is movably arranged on the other side of the supporting base; a thread fixing assembly is arranged on the movable bracket; the rotation driving mechanism comprises a telescopic supporting assembly and two overturning driving assemblies; the movable support is further provided with a movable overturning assembly. According to the pressure vessel submerged-arc welding external welding device and the external welding method thereof, hoisting movement of the tank body and the tank bottom is facilitated, and when the tank body and the tank bottom are driven to turn over, it can be guaranteed that the tank body and the tank bottom turn over stably.

High pressure compressed gas pressure vessels and devices utilizing such vessels are disclosed herein. More particularly, aspects of the present invention are directed to high pressure (i.e., nitrogen or N2 based) pressurized gas cylinders with pierceable membranes recessed from the opening of the pressure vessel such that prior art piercing mechanisms cannot pierce the membrane for safety purposes. Additionally, aspects of the present invention are directed to pressurized gas operated devices with elongated pins for piercing pressure vessels with recessed pierceable membranes.

According to the hydrogen storage bottle inner container high pressure resistance detection equipment and detection method, the service performance of a non-pressure-bearing inner container under the high pressure condition can be directly detected through a method of simultaneously applying high pressure inside and outside the inner container, controlling the temperature of a pressure medium and controlling a BOSS structure on the right side of the inner container to axially move along with the pressure of the medium; furthermore, a recyclable, easy-to-process and non-pressure-bearing hard shell is manufactured outside the inner container, so that the deformation of the inner container during testing is efficiently controlled to be consistent with the deformation of the inner container in the hydrogen storage bottle at low cost; more importantly, aiming at the problem that signals are difficult to transmit outwards in a wired mode in a high-voltage container, a high-voltage-resistant signal line interface structure and a related expansion structure are designed, and wired signal transmission between high voltage and low voltage can be achieved.

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.