13313results about "Nuclear energy generation" patented technology

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 discloses a radioactive substance multi-point synchronous detection and identification method and system, and relates to the technical field of radioactive substance monitoring. Comprising the following steps: step 1, collecting multi-point radiation data in real time, and preprocessing and storing the data; step 2, constructing a spatial adjacency matrix, estimating a local spatial gradient, calculating an anomaly degree value, taking optimization measures, and performing collaborative anomaly evaluation on the monitoring nodes; 3, calculating a total fitting error value, reversely deducing a leakage source position and leakage intensity in real time, and taking corresponding measures in real time; 4, abnormal trend identification is carried out, an early warning judgment value is calculated, and graded early warning and multi-node cross confirmation measures are implemented; and 5, receiving and storing various types of data, carrying out visualized analysis on the data, and supporting event processing and feedback. The problems that due to the fact that some devices are good in shielding and have physical obstruction, trace leakage is difficult to detect by a single-point monitor, and the risk of long-term retention pollution exists are solved.

The invention discloses a coil connecting device for a star imitator magnet and the star imitator magnet, the coil connecting device comprises a shell, a first connecting part and a second connecting part, and a movable space is formed between the outer peripheral surface of each connecting part and the inner wall surface of an accommodating space and between the outer peripheral surface of each connecting part and a connecting hole. The first part of the first connecting part and the second connecting part can relatively rotate around the axial direction of the shell, so that the first connecting part and the second connecting part have a certain degree of freedom of movement in the radial direction of the shell and can adapt to irregular changes of adjacent surfaces of adjacent coils in the radial direction; and the risks of plastic deformation, fatigue cracks and fracture of the connecting part can be reduced.

The invention discloses a cooling pipeline assembly for a fusion reactor, and relates to the technical field of fusion reactors. The cooling pipeline assembly comprises a fixed base, a supporting part and a buffer part, and a supporting column extending in the height direction is arranged on the fixed base; a mounting part is formed at at least one end of the supporting part in the width direction, a mounting hole is formed in the mounting part, the mounting hole is through in the height direction and extends in the front-back direction, and the supporting column can move in the mounting hole in the front-back direction; the buffering piece is connected with the supporting column and the mounting part and used for keeping the supporting column and the mounting part at the preset position, and the buffering piece is suitable for deforming when the supporting part is driven to move relative to the fixed base after the pipeline deforms so as to adjust the relative position of the supporting column and the mounting part. According to the cooling pipeline assembly, through mutual cooperation of the fixing base, the supporting component and the buffering piece, the supporting component can move along with thermal deformation of the pipeline, stress concentration is relieved, and safe and stable operation of the cooling pipeline assembly and a fusion reactor is guaranteed.

The invention provides an ultra-short beam homogenization transmission line system and method based on a four-eight-pole composite magnet. The system comprises the four-eight-pole composite magnet, a system, a linear beam homogenization structure, a bent beam homogenization structure and secondary iron used for a beam homogenization transmission line. The system further comprises an ultra-short linear beam homogenization transport line, an ultra-short bent beam homogenization transport line, an ultra-short linear bent composite beam homogenization transport line and an ultra-short symmetrical bent beam homogenization transport line based on the homogenization structure and / or the dipolar iron. The method comprises an exciting current debugging method based on the four-pole and eight-pole composite iron and a linear type and bending type beam debugging method. According to the invention, the problem that the maximum enveloping part on the transmission line is occupied and the effect of octopole iron cannot be fully exerted is solved; the problems that the beam envelope of the position where the octopole iron is located is small, and the requirement for the field intensity of the octopole magnet is high are solved. The problem that the civil engineering shielded around the transmission line is more expensive because the transmission line is too long is solved.

The invention discloses a pulsed eddy current detection method and system for a thermal power pipeline with a coating layer, and relates to the technical field of pulsed eddy current nondestructive detection.The pulsed eddy current detection method comprises the steps that pulsed eddy current detection simulation and experiment are conducted under the condition of a three-dimensional simulation model and a test piece, and excitation current waveform, amplitude and frequency parameters are determined; an induced voltage signal is collected, peak values, time points and attenuation characteristics are extracted, the corresponding relation between the wall thickness, the coating layer thickness and the welding seam structure and detection signals is constructed, a parameterized database is constructed, and temperature correction is completed; and optimizing a sensor structure and a signal acquisition scheme according to a parameterized database, obtaining detection data in a pipeline operation state, completing two-dimensional imaging of wall thickness distribution and welding seam positioning, and forming detection information covering a straight pipe, an elbow and a welding seam area. According to the method, wall thickness detection and welding seam positioning of the thermal power pipeline under the conditions of a thick wall and a thick coating layer are achieved through the full-process design of test piece modeling, simulation experiment and imaging collection.

The invention relates to the technical field of fusion reaction devices, and discloses a flexible electrical connection structure and a fusion reaction device, and the flexible electrical connection structure comprises a first installation assembly, a second installation assembly and a connection assembly. The first installation assembly comprises an installation base, a supporting piece and an adjusting base, the supporting piece is connected with the installation base and can move in the first direction relative to the installation base, the adjusting base is connected with the supporting piece and can move in the second direction relative to the supporting piece, and the second direction is perpendicular to the first direction. One end of the connecting assembly is connected with the adjusting seat, the other end of the connecting assembly is separably connected with the second mounting assembly, and the first mounting assembly, the connecting assembly and the second mounting assembly can form a conductive path. Therefore, the position of the connecting assembly can be adjusted through movement of the supporting piece and the adjusting seat. In the installing process or the working process, the position of the connecting assembly can be adjusted in a self-adaptive mode, the overall installing efficiency of the fusion reaction device is improved, and the connecting stability of the connecting assembly and the second installing assembly in the working process is improved.

The invention relates to the technical field of nuclear fusion, and discloses a supporting device and a method for assembling a vacuum chamber and a cold shield of a nuclear fusion device.The supporting device comprises a first supporting assembly and a second supporting assembly, the first supporting assembly comprises a first clamping piece, a first supporting piece and a first adjusting piece, and the first clamping piece and the first supporting piece are spaced in the first direction and connected through the first adjusting piece; the first adjusting piece can adjust the distance between the first clamping piece and the first supporting piece in the first direction. The second supporting assembly comprises a second clamping piece, a second supporting piece and a second adjusting piece, the second clamping piece and the second supporting piece are spaced in the first direction and connected through the second adjusting piece, and the second adjusting piece can adjust the distance between the second clamping piece and the second supporting piece in the first direction; the third adjusting piece is connected with the first supporting piece and the second clamping piece and can adjust the distance between the first supporting piece and the second clamping piece in the first direction. The cold shield and the vacuum chamber can be clamped, and the gap between the cold shield and the vacuum chamber can be adjusted.

The invention relates to the field of nuclear fusion, and discloses a fixing device for a nuclear fusion preassembled assembly, and the fixing device comprises a magnet connecting assembly which comprises a first beam body and a magnet connecting part, the first beam body extends in a first direction, and the magnet connecting part is arranged on the first beam body; the vacuum chamber connecting assembly and the magnet connecting assembly are spaced in the second direction, the vacuum chamber connecting assembly comprises a second beam body and a vacuum chamber connecting part, the second beam body extends in the first direction, and the vacuum chamber connecting part is arranged on the second beam body; the beam body connecting assembly is arranged at the two ends of the second beam body in the first direction, is connected with the first beam body and comprises a first connecting piece, a second connecting piece and an elastic energy storage piece, the first connecting piece is movably connected with the second connecting piece and is detachably connected with the first beam body, and the second connecting piece is detachably connected with the second beam body; one end of the elastic energy storage piece is movably connected with the first connecting piece, and the other end is movably connected with the second connecting piece. The gap between the magnet and the vacuum chamber can be restrained, and the position precision between the magnet and the vacuum chamber is guaranteed.

The invention relates to the technical field of pipeline detection, in particular to an infrared thermal imaging full-dimensional monitoring method for corrosion of a pipeline under a thermal insulation layer, which comprises the following steps of: acquiring temperature distribution under the thermal insulation layer and screening measuring points with consistent directions, extracting a boundary continuous region to calculate thermal probability, identifying abnormal measuring points and extracting time sequence characteristics, and predicting and marking response delay measuring points based on a model. And generating a CUI risk region division result. According to the method, a temperature difference direction consistency identification mechanism is constructed through space sequence subdivision and heat flow direction trend judgment of pipeline surface temperature distribution data, a measurement point set with clear space heat conduction characteristics is obtained through continuous screening, and a gradient change rate local extreme value is further taken as an identification basis; the method comprises the following steps: constructing a thermal anomaly probability evaluation parameter by combining spatial density and change intensity to realize preliminary identification of an abnormal point, then introducing a time sequence temperature parameter to construct a multi-dimensional dynamic feature set, and completing multi-step temperature prediction through normalized combination calculation after model training.

The invention relates to the technical field of high temperature sensing and data fusion, in particular to a method for array thermocouple multi-mode compensation and DIC stress field space-time coupling fusion, which comprises the following steps: step 1, in a thermotechnical signal intelligent processing and compensation unit, completing hardware and algorithm collaborative design of an electronic cold junction compensation module; 2, constructing a multi-algorithm fusion compensation module, integrating nonlinear correction, drift compensation and interference suppression functions, and accurately coping with various interference signals through a dynamic weighting strategy; step 3, adopting a sub-pixel-level matching algorithm and a homography matrix calibration technology to realize high-precision space alignment of the temperature and stress measurement units; and establishing a nonlinear incidence relation between the temperature and the stress based on an improved Gaussian process regression model. According to the invention, based on collaborative design of the thermotechnical signal intelligent processing and compensation unit and the DIC vision and temperature data conjoint analysis module, the core precision problem of temperature and stress detection in a high-temperature environment is solved through hardware optimization and algorithm innovation.

The invention belongs to the technical field of nuclear fusion devices, and discloses a tool and method for adjusting a Dewar bottom side ring body cold shield in a PIT foundation pit. Wherein in the adjusting tools, two first adjusting tools and two second adjusting tools are detachably fixed on a first isolation block and a second isolation block in an in-place mounting area of the Dewar base and are used for adjusting the horizontal position precision and the vertical position precision of a to-be-mounted cold shield module on the hoisting tool; the temporary supporting tool is detachably fixed to a third isolation block on a Dewar base at intervals along the circumference and used for supporting the bottom of a Dewar bottom side ring body cold shield formed by annularly connecting a plurality of to-be-installed cold shield modules and adjusting the vertical position precision of the Dewar bottom side ring body cold shield. According to the invention, the to-be-mounted cold shield module with large size and heavy weight can be mounted at high precision in a narrow mounting space in a PIT foundation pit, the Dewar base is not polluted, and the disassembly and assembly are convenient.

The invention provides a multi-objective optimization method for non-planar coils of a star simulator and a star simulator magnet. The optimization method comprises the following steps: obtaining initial structures of a plurality of non-planar superconducting coils according to magnetic field configuration data of target plasma; according to the target magnetic field parameter, the engineering constraint parameter and the material constraint parameter of the configuration data, an objective function is constructed, the engineering constraint parameter comprises the engineering limit geometric parameter of the non-planar superconducting coil, and the material constraint parameter comprises the limit current carrying of the non-planar superconducting coil material; carrying out minimization solution on the target function to obtain optimized coil data; and performing materialization processing on the plurality of non-planar superconducting coils according to the optimized coil data to obtain a plurality of optimized non-planar superconducting coil models. According to the optimization method, a magnetic field matching-engineering feasibility-material safety three-dimensional constraint system is constructed, and the problem that the engineering cannot be realized on the ground is avoided.

The invention provides a method and a system for measuring plasma current in a quasi-ring symmetrical star simulator, and relates to the technical field of star simulators, and the method comprises the steps: determining a sensor design index according to a bootstrap current simulation calculation result, and converting the design index into an actual arrangement scheme according to an installation environment constraint; all the magnet coils are independently excited in a plasma-free state, wall eddy current interference signals generated by the magnet coils are calibrated, and thus wall eddy current calibration voltage signals are output; a sensor in an actual arrangement scheme is used for synchronously collecting a total original induced voltage signal including plasma current and wall eddy current; an integral voltage signal representing the total current is output; and compensating the integral voltage signal by using the wall eddy current calibration voltage signal, and inverting the final measurement value of the plasma current in the quasi-ring symmetric star simulator. The device and the method have the beneficial effects that the interference of a stray field on a measurement result is weakened, and a high-precision diagnostic tool is provided for the plasma physical research of the star simulator.

A control method and system for controlling a nuclear power plant includes, in the absence of detection of an imbalance between a primary power signal (S1) and a secondary power signal (S2), the implementation of a setpoint-following mode. The nuclear power plant is controlled as a function of an operational power setpoint (COP), and in the event of detection of an imbalance, automatically implementing a power-limiting mode, including the calculation of a target equilibrium power (PEC) less than or equal to the primary power (P1) and less than or equal to the secondary power (P2), and controlling the nuclear power plant (2) as a function of the target equilibrium power (PEC).

The invention discloses a dynamic monitoring-based deaerator water supply control method and system for a nuclear power plant, and relates to the field of deaerator water supply control, and the method comprises the steps: firstly, through a hybrid online identification algorithm, analyzing a historical valve position instruction and a water supply flow sequence in real time, and dynamically estimating the local gain and hysteresis width of a valve under the current working condition; then, the parameters identified in real time are utilized to carry out prospective compensation on the expected flow variation calculated by the main controller. In other words, the instruction amplitude is adjusted according to the estimated local gain, and it is ensured that consistent flow response can be obtained under different loads; meanwhile, when the instruction is reverse, the compensation amount is actively applied according to the estimated hysteresis width so as to eliminate the adjustment dead zone and oscillation caused by hysteresis. In this way, the nonlinear object of the valve is equivalent to a linear link with consistent response, and the stability and accuracy of the deaerator water level control system in the full working condition range are remarkably improved.

The invention relates to the field of reactor data processing, and particularly discloses a numerical calculation method for solving a neutron transport equation. The method comprises the following steps: 1, describing the geometry of a reactor core of a nuclear reactor by utilizing a construction entity geometric modeling method, and subdividing a curved surface grid along a curved surface structure; 2, directly expanding a neutron flux distribution function in each curved surface grid by using a multivariate polynomial; 3, deriving a neutron transport equation and an integral residual equation of a boundary condition under each curved surface grid; 4, solving geometric integral parameters of each curved surface grid; step 5, establishing an adaptive linear system; and step 6, iteratively calculating and solving a maximum characteristic value and an unknown expansion coefficient.

The invention provides a samarium / europium / gadolinium-containing zirconium hydride block as well as a preparation method and application thereof, and relates to the technical field of radiation shielding materials. The zirconium hydride block containing samarium / europium / gadolinium comprises the following elements in percentage by mass: 95% < = Zr < = 99.5%, 0% < = Gd < = 5%, 0% < = Sm < = 5%, 0% < = Eu < = 5% and 0% lt. Gd + Sm + Eu < = 5%. The preparation method comprises the following steps: respectively hydrogenating sponge zirconium, metal gadolinium, metal europium and metal samarium to respectively obtain corresponding hydride powder; weighing zirconium hydride powder, gadolinium hydride powder, europium hydride powder and samarium hydride powder according to a required proportion, and uniformly mixing under a protective atmosphere; and carrying out pressure sintering on the mixed powder, and carrying out secondary hydrogenation to obtain the zirconium hydride block containing samarium / europium / gadolinium. According to the invention, the absorption of the material to low-energy-segment neutrons can be obviously improved; and the preparation of the zirconium hydride block containing samarium / europium / gadolinium and the accurate regulation and control of doped elements are realized.

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.

The invention discloses a self-adaptive control method and system for a condenser for a nuclear power station, relates to the field of condenser control, and aims to predict a future load change trend in a prospective manner by analyzing historical data of a unit power instruction and steam flow, and calculate feed-forward circulating water flow based on a prediction result. On the basis, a feedback control loop based on actually measured pressure is reserved. More importantly, a self-adaptive bias correction mechanism is introduced, and continuous learning and correction are carried out on output of feedback control, so that steady-state errors of the system are eliminated, and uncertainty of the model is compensated. Finally, feed-forward, feedback and self-adaptive correction components are intelligently fused to form a final control instruction which can quickly respond to load changes and can accurately maintain pressure stability, and the problems of severe pressure fluctuation and energy waste under the dynamic working condition are effectively solved.

The invention discloses a reactor instrument control system equipment fault early warning method and related equipment, and relates to the technical field of reactor operation and maintenance, and the technical scheme is characterized in that the method comprises the following steps: obtaining operation parameters of target equipment of a reactor instrument control system in real time, and synchronously collecting historical operation data and historical fault data of the target equipment at the same time; constructing a machine learning analysis model, and training the machine learning analysis model by taking the historical operation data and the historical fault data as training samples; running parameters collected in real time are input into the trained machine learning analysis model, abnormal features representing the change trend and the deviation degree of the real-time parameters are output, a preset equipment abnormal feature library is matched based on the abnormal features, whether the target equipment has faults or not is judged, and a health degree index representing the health state of the target equipment is calculated; and if the fault judgment result is that the potential fault exists or the health degree index is lower than the preset health threshold value, generating a corresponding fault early warning signal and a health degree evaluation result.

The invention discloses a fuel rod cladding surface corrosion product deposition test device and method, and belongs to the field of nuclear power. The fuel rod cladding surface corrosion product deposition test device comprises a water supply section and a test section, the test section comprises a high-pressure kettle and a cladding pipe contained in the high-pressure kettle, and a heater is arranged in the cladding pipe to simulate heating of a fuel rod; the water supply section is used for providing circulating solution for the test section and comprises a coolant water tank, a dirt source water tank, a heating device, a pump set and a circulating pipeline, the coolant water tank circularly intervenes in the circulating pipeline to provide circulating simulated coolant, the dirt source water tank is used for injecting simulated dirt liquid into the circulating pipeline, the pump set is used for providing driving force, and the heater is used for heating. The device can accurately control the hydrochemical conditions of the dirt deposition test, keeps the consistency and repeatability of the test conditions in the test process, effectively improves the simulation test precision, and optimizes the test efficiency.

The invention provides a space measurement and analysis method and system for a neutron diffraction rocking curve of a single crystal material, and the method comprises the steps: S1, building a laboratory coordinate system and a sample coordinate system, and setting a test point grid; s2, collecting a two-dimensional diffraction image of each test point to obtain angle information of the test point; s3, integrating the angle information of the test points based on the test point grid, and preprocessing the two-dimensional diffraction image; s4, extracting key structure parameters of each test point based on the preprocessed two-dimensional diffraction image; s5, constructing a stress field according to the key structure parameters; and S6, constructing a distribution map of crystal internal lattice parameters in a three-dimensional space according to the stress field. The method provided by the invention effectively improves the capability of identifying the non-uniformity and local distortion of the crystal structure, can be widely applied to the fields of residual stress evaluation, defect evolution monitoring, material quality control and the like, and has a remarkable engineering application value.

The invention particularly relates to a discharge machining simulation control system for a nuclear power plant in a high-radiation boron-containing water environment, which belongs to the technical field of special maintenance in the high-radiation environment of the nuclear power plant and comprises a man-machine interaction system, a discharge machining control system and subsystems. Each subsystem comprises a pulse power supply system, a servo power system, a washing system, a purification system, a grounding system and a tool system; the man-machine interaction system is used for man-machine interaction and displaying the discharge machining implementation data fed back by the subsystems; the electric discharge machining control system is used for generating an electric discharge machining instruction according to the man-machine interaction information and controlling the subsystems to cooperate to perform electric discharge machining work; and each subsystem is used for implementing electric discharge machining work according to the electric discharge machining instruction and feeding back electric discharge machining implementation data. According to the invention, simulation control of discharge processing in the high-radiation boron-containing water environment of the nuclear power plant is realized.

The invention relates to the field of nuclear fusion, and discloses a transition feeder line assembling device and a transition feeder line assembling method, and the assembling device comprises an assembling platform, a first adjusting part, a second adjusting part, a guide rail and a supporting assembly. The first adjusting piece and the second adjusting piece are arranged on the assembling platform in a spaced mode in the first direction and are configured to move in the second direction and the third direction, and the first direction, the second direction and the third direction are perpendicular to one another; the guide rail extends in the first direction, one end of the guide rail is detachably arranged on the first adjusting piece, and the other end of the guide rail is detachably arranged on the second adjusting piece. The multiple supporting assemblies are arranged on the guide rail at intervals in the first direction, each supporting assembly comprises a sliding part and a clamping part, the sliding parts are arranged on the guide rail, and the clamping parts are arranged on the sliding parts. According to the assembling device of the transition feeder line, the transition feeder line can be prevented from toppling or deforming in the installation process, the efficiency and precision of installation of the transition feeder line are improved, and the reliability of the transition feeder line is further improved.

The invention relates to the technical field of nuclear fusion devices, and discloses a fusion device cooling pipe welding method and welding device.The fusion device cooling pipe welding method comprises the following steps that two cooling pipes to be welded are prepared; an adapter is welded to the welding face of one cooling pipe, and the nickel content of the adapter is higher than that of the cooling pipe; the radial interior of the adapter and the to-be-welded face of the adapter are polished; the two cooling pipes are assembled, so that the welding face of the other cooling pipe is in butt joint with the to-be-welded face of the adapter; and carrying out self-fusion welding on the adapter and the other cooling pipe. According to the welding method for the cooling pipe of the fusion device, the problem that the magnetic conductivity of the cooling pipe exceeds the standard is solved, and meanwhile the welding quality and the welding qualification rate of the cooling pipe are improved.

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 field of nuclear fusion device installation, and discloses a supporting device of a nuclear fusion device preassembled assembly, and the supporting device of the nuclear fusion device preassembled assembly comprises a first supporting section, a second supporting section and an adjustable supporting section which are detachably connected in sequence along a first direction; the adjustable supporting section comprises a first adjusting part, a second adjusting part and a lifting part which are sequentially connected in the first direction, the first adjusting part is connected with the second supporting section and can drive the second adjusting part to be adjusted in the second direction, the second adjusting part can drive the lifting part to be adjusted in the third direction, and the lifting part can be adjusted in the first direction in a lifting mode. The first direction, the second direction and the third direction are perpendicular to one another. The supporting device of the preassembled assembly of the nuclear fusion device can support the bottom of the preassembled assembly, the position precision of the preassembled assembly can be improved, and the installation reliability of the nuclear fusion device is improved.

The invention discloses a low-temperature pump for a fusion device and the fusion device, and relates to the field of fusion devices.The low-temperature pump comprises a low-temperature pump body, an adsorption space is defined by the low-temperature pump body, and a first medium inlet communicating with the adsorption space is formed in the low-temperature pump body; the valve assembly is arranged on the cryogenic pump main body, and the valve assembly is used for opening or closing the first medium inlet; and at least part of the adsorption assembly is arranged in the adsorption space, the adsorption assembly is used for adsorbing gas in the adsorption space, and the adsorption assembly is detachably arranged on the cryogenic pump body. Therefore, the adsorption assembly is detachably arranged on the cryopump main body, the adsorption assembly can be independently replaced, the maintenance cost of the cryopump can be reduced, the production cost of fusion energy can be reduced, the economic benefit is further improved, and the adsorption assembly can be replaced without shutdown under the condition that a certain adsorption assembly is replaced.

The invention provides monitoring equipment and system for monitoring a reactor core of a nuclear power plant. The monitoring device comprises a data preprocessing module, a model updating module, a monitoring module, a shared data pool and a monitoring interface module. On one hand, on-line monitoring of a reactor core is realized by tracking actual operation data of a reactor, and the accuracy of a monitoring result is improved; and on the other hand, the reactor core three-dimensional power distribution reconstruction is carried out in combination with the actual measurement current, so that the monitoring result (such as the second reactor core physical parameter) obtained based on the reconstructed reactor core three-dimensional power distribution is more matched with the actual operation condition of the reactor core, and the accuracy is higher.