18922results about "Nuclear energy generation" patented technology

The invention discloses an assembling method and an assembling tool for a bottom cold shield side plate of a fusion reactor, the bottom cold shield side plate is constructed into a ring shape defined by a plurality of side plates, and the assembling method for the bottom cold shield side plate of the fusion reactor comprises the following steps: the plurality of side plates are assembled into a sector; the plurality of sectors are assembled into a ring at the Dewar base of the host hall. According to the assembly method of the bottom cold shield side plate of the fusion reactor, the plurality of side plates are assembled into the sector section, and then the plurality of sector sections are assembled into the ring at the Dewar base of the host hall, so that the bottom cold shield side plate can well meet the assembly requirement in a narrow space when being assembled; and the installation difficulty and the assembly cost of the bottom cold shield side plate are well reduced.

A nuclear fusion reaction device, system and method. The outer wall of a vacuum chamber (301) in the nuclear fusion reaction device (30) comprises an inner ring surface (M1) and an outer ring surface (M2) which are connected to each other; the outer ring surface (M2) surrounds the inner ring surface (M1); the inner ring surface (M1) protrudes toward the central axis of the vacuum chamber (301); the vacuum chamber (301) surrounds a plurality of first coils (302); at least some of the plurality of first coils (302) extend in the circumferential direction of the inner ring surface (M1) and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of second coils (303) surround the vacuum chamber (301), extend in the circumferential direction of the outer ring surface (M2), and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of third coils (304) all surround the vacuum chamber (301) and are sequentially arranged in the circumferential direction of the vacuum chamber (301); and the plurality of first coils (302), the plurality of second coils (303), and the plurality of third coils (304) are used for generating a magnetic field, such that plasma rings with negative triangular deformation are generated in the vacuum chamber (301), and a fusion reaction occurs.

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 relates to the technical field of nuclear fusion devices, and discloses a nuclear fusion device and a monitoring system and an installation method thereof, the monitoring system comprises a cold shield main body, the cold shield main body is of an annular rotation structure, and the cold shield main body is arranged in a cavity and wraps the circumferential outer side of a vacuum chamber; the cold shield main body comprises a plurality of groups of fan-shaped cold shield sections which are sequentially arranged in the circumferential direction, and the plurality of groups of fan-shaped cold shield sections are encircled to form the cold shield main body; the distance measuring assembly is arranged on the cold shield main body, the distance measuring assembly comprises a plurality of groups of distance measuring sensors which are arranged in the circumferential direction of the cold shield main body at intervals, and each group of distance measuring sensors comprises a plurality of distance measuring sensors; the distance measuring sensor is used for detecting the size of a gap between the cold shield body and the longitudinal field coil and the size of a gap between the cold shield body and the vacuum chamber. Therefore, the cold shield main body can be assisted to be assembled at a position in the nuclear fusion device, and the matching position of the cold shield main body, the vacuum chamber and the longitudinal field coil can be monitored in real time.

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.

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.

A grouting simulation test system and method for high-temperature water-rich filled fractures. The grouting simulation test system comprises: a water head intelligent sensing and adjusting module, a fracture medium intelligent simulation module, a double-liquid grouting module, a data analysis module, and an intelligent control module. The fracture medium intelligent simulation module comprises a water bath circulation temperature control unit, a fracture model (11), and an opening degree adjustment unit. The water bath circulation temperature control unit is arranged on upper and lower sides of the fracture model (11). Circulating water is provided in the water bath circulation temperature control unit, and the temperature of the circulating water is controllable. The fracture model (11) is formed by combining a plurality of model units. The opening degree adjustment unit is connected to the water bath circulation temperature control unit above the fracture model (11) and is capable of raising and lowering the water bath circulation temperature control unit. The present test system can achieve the study of a grouting diffusion mechanism under the coupling action of two or more factors such as different slurry properties, dynamic water flow velocity, dynamic water temperature, fracture medium multivariate factors, medium temperature, and filling conditions.

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

The invention discloses a tool suitable for laser interferometer light beam collimation and a laser interferometer light beam collimation method. The tool comprises a workbench, a workpiece table, a vacuum cavity, a laser interference measuring device and a debugging device. The vacuum cavity is arranged on the working table, the workpiece table is arranged in the vacuum cavity, and the laser interference measuring device is fixedly arranged on the working table and is used for performing high-precision displacement measurement on the workpiece table in the vacuum cavity; the debugging device is movably arranged on the workbench and used for light path collimation. According to the invention, collimation of all optical paths is completed by using a universal installation and adjustment tool, so that the cost is greatly reduced, the universality and operability of the collimation method are improved, and the method is easy to popularize.

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.

According to the auxiliary supporting mechanism for assembling the internal parts of the Tokamak and the assembling method, all auxiliary stand columns and a center stand column are installed at the same center distance, and the center stand column is provided with an upper-layer disc-type turn buckle supporting mechanism and a lower-layer disc-type turn buckle supporting mechanism so as to be connected with the outer surface of a vertical section of a vacuum chamber ring petal; the outer side supporting mechanism is connected around the outer surface of the vacuum chamber ring valve set, the double-column type bottom supporting table is located below the vacuum chamber ring valve set, and the vacuum chamber ring valve set is supported from the outer side and the lower portion of the vacuum chamber ring valve set; a stand column connecting rod is connected between every two adjacent auxiliary stand columns, and a limiting mechanism capable of extending into a window in a vacuum chamber ring petal is installed on each stand column connecting rod. The U-shaped operation platform penetrates through the vacuum chamber ring petal set, and a plurality of small internal part assembling auxiliary tools are movably installed on the surface of the U-shaped operation platform. The method is wide in application range, can effectively solve the problems that transportation channels of internal parts are few and the assembly construction space is limited, and reduces the construction difficulty and the construction cost.

The invention discloses a method for processing foreign matters in the lower reactor internals of a reactor, which comprises the following steps of: completing global video inspection of the lower reactor internals of the reactor through a video inspection mechanism, determining whether foreign matters exist or not, and determining the positions, the sizes and the types of the foreign matters according to global images of the lower reactor internals of the reactor acquired by the video inspection mechanism. A data processing module of the position navigation mechanism is used for determining a corresponding drain hole area number of the target foreign body, a mechanical arm body type of the mechanical arm mechanism, a gripping apparatus type of the gripping mechanism and an initial movement posture of the mechanical arm mechanism; and the remote control operation mechanism is used for operating the mechanical arm mechanism to move and operating the grabbing mechanism to accurately grab the target foreign matter. According to the method, a high-efficiency full-area inspection and foreign matter grabbing method capable of covering the reactor internals at the lower part of the reactor is formed, the traditional mode that the reactor internals at the lower part of the reactor are firstly hoisted out of the pressure vessel and then the foreign matter is grabbed is changed, and the risk of damage to the reactor internals and the pressure vessel body is reduced.

This application relates to a test device applied to a coupled environment of stress, wear, and corrosion, and a quantitative evaluation method, and belongs to the field of failure analysis of materials. The test device includes a stress-loading mechanism configured to load a stress on a sample, a corrosion mechanism configured to conduct an electrochemical corrosion test on the sample, and a wear mechanism configured to wear a sample. The test device applied to a coupled environment of stress, wear, and corrosion of this application can establish a wear-stress-corrosion coupled action test process, and can investigate service behaviors of various metallic materials and metal matrix composites under conditions close to actual service conditions to obtain key behavior data under a multi-factor coupled action, quantitatively analyze a wear, a corrosion, a wear-corrosion interaction, a stress-wear interaction.

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 a pipeline defect ultrasonic detection device, and relates to the technical field of pipeline detection.The pipeline defect ultrasonic detection device comprises a supporting box, a moving assembly, an adjusting assembly, a smearing assembly and an ultra-detection assembly, the moving assembly, the adjusting assembly and the smearing assembly are all arranged on the supporting box, and the ultra-detection assembly is arranged on the smearing assembly; the moving assembly is used for linearly and rapidly driving the supporting box to move in the pipeline and spirally and slowly driving the supporting box to move in the pipeline, the adjusting assembly is used for enabling the moving assembly to switch a linear rapid driving mode and a spiral slow driving mode, and the smearing assembly is used for smearing a coupling agent. The super-detection assembly is used for conducting spiral flaw detection on the inner wall of the pipeline in the process that the smearing assembly smears the coupling agent. The device has the effect that the ultrasonic probe can carry out comprehensive flaw detection on the whole inner wall of the flaw detection part of the pipeline.

The invention provides a method for calculating the heat release rate of an isotope irradiation target of a pebble-bed high-temperature gas cooled reactor, and the method comprises the steps: constructing a reactor model of the pebble-bed high-temperature gas cooled reactor through a special design application, so as to calculate the nuclear fuel component distribution of a reactor core; carrying out two times of non-uniform arrangement on the reactor core fuel distribution through the MC application program to construct a reactor core MC model, and transmitting the nuclear fuel component distribution of the reactor core to the reactor core MC model; calculating a plurality of energy deposition heat release rates of the isotope irradiation target through a target Monte Carlo model for isotope irradiation production, and calculating a plurality of decay heat release rates of isotopes generated by irradiation; and adding the multiple energy deposition heat release rates and the multiple decay heat release rates to obtain the isotope irradiation target heat release rate of the pebble-bed high-temperature gas cooled reactor. According to the method, the heat release rate of the isotope irradiation target can be accurately calculated according to the characteristics of dual heterogeneity and non-stop refueling of the pebble-bed high-temperature gas cooled reactor.

The present application relates to the technical field of carbon / carbon composite materials, and specifically discloses a carbon-carbon guide tube and a preparation method thereof. The preparation method of the carbon-carbon guide tube comprises: cutting carbon fibers into short fibers, combing the short fibers into a mesh; immersing the mesh into an impregnation liquid in the equipment to obtain a pre-impregnated mesh; laying multiple layers of impregnated mesh on the surface of a mold; curing the multiple layers of impregnated mesh on the mold, demolding to obtain a blank; carbonizing and graphitizing the blank; subjecting the graphitized blank to a chemical vapor deposition densification process and a pyrolytic carbon coating process in sequence to obtain a carbon-carbon guide tube. The method for preparing the carbon-carbon guide tube does not require the preparation of a preform, thereby eliminating the problem of carbon fiber waste generated during the manufacturing process of the preform, and can shorten the manufacturing cycle, improve production efficiency, and reduce production costs. The carbon-carbon guide tube prepared by the method has good mechanical properties and corrosion resistance, and can meet the use requirements of the guide tube for the thermal field of a photovoltaic direct-pull single crystal silicon furnace.

The invention discloses an inner blowout prevention tool nonmetal part tensile test tool and a test method thereof, and belongs to the technical field of tensile tests.The inner blowout prevention tool nonmetal part tensile test tool drives two test assemblies to conduct position exchange by switching a feeding assembly, so that a clamped sample can be smoothly located in an arc-shaped cover to conduct side tensile test operation, and the test efficiency is improved. Double-station switching type feeding operation is adopted, continuous feeding operation can be achieved in a reciprocating mode, the sample testing efficiency can be greatly improved through double-station switching type feeding, secondly, a protection plate in a switching feeding assembly can be matched with an arc-shaped cover to keep a closed machining area, the stretching safety is guaranteed, and in the rotating process of the testing assembly, the machining efficiency is greatly improved. And a rolling ball in a limiting assembly is driven to extrude the side edge of an arc-shaped cover, so that the rolling ball can push an upper second piston rod to move, the upper second piston rod can drive a third piston rod to move through hydraulic pressure, a clamping tooth plate is meshed with a third gear, the position of a stud can be locked, and therefore the clamping firmness of the sample can be effectively improved.

The invention provides a pressurized water reactor scale-caused axial power offset risk coupling calculation method and device. The method comprises the following steps: performing corrosion scale thickness deposition simulation by using a first calculation module, and calculating to obtain cooling liquid temperature distribution in the axial direction of a fuel rod and corrosion scale deposition thickness distribution in the axial direction of the fuel rod; a second calculation module is used for carrying out enrichment simulation on boron elements in the corrosion scale deposits and calculating the boron concentration distribution condition in the corrosion scale deposits of each layer in the axial direction; and performing fuel rod axial power distribution simulation by using a third calculation module, and calculating to obtain a scale-caused axial power offset value according to the corrosion scale thickness distribution and the boron concentration distribution condition. The scale-caused axial power offset value is predicted by adopting a multi-module, multi-physical-field and multi-scale coupled calculation method, so that the technical problem of how to comprehensively consider the effects of multiple scales and multiple physical fields to predict and analyze corrosion scale deposition is solved.

The invention relates to the technical field of laser welding, and discloses a laser machining device and method for a nuclear reactor shell, and the method comprises the steps that a shell plate welding area to be welded is subjected to surface modification pretreatment; the laser processing device is used for carrying out initial welding on the pretreated shell plate, in the initial welding process, the temperature sensing assembly is used for monitoring temperature distribution of the welding area in real time, and temperature information of the welding area is obtained; the temperature information is input into a preset temperature-deformation prediction model for prediction of a variable trend and a stress distribution condition so as to obtain a first prediction result; based on the obtained first prediction result, the welding parameters of the laser processing device are dynamically adjusted for the first time; welding deformation and stress concentration are effectively coped with, the welding quality and structural strength of the nuclear reactor shell after laser welding are improved, and the reliability and safety of the nuclear reactor shell during use are effectively improved.

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

The invention 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 discloses a method and device for measuring flow-induced vibration of a plate-type fuel assembly, and belongs to the field of nuclear power. The flow-induced vibration measurement method for the plate-type fuel assembly comprises the following steps: firstly, carrying out a flow-induced vibration test on a fuel plate of which the two ends are clamped and fixed, and carrying out measurement to obtain strain data and displacement data of a measurement point location on the fuel plate; establishing a simulation model of the fuel plate, simulating a flow-induced vibration behavior, verifying a calculation result and measurement data, and iterating the simulation model according to a verification result to obtain a calibration model with an error smaller than a given threshold value; a plate-type fuel assembly test piece with a plurality of fuel plates is used for carrying out a flow-induced vibration test, strain data of corresponding measurement points of the fuel plates are measured, and corresponding flow-induced vibration displacement data are given according to the strain data by using a calibration model. The invention further provides a plate type fuel assembly flow-induced vibration measuring device.

The invention provides a method for obtaining a cell survival score model based on different depths, a terminal and a medium, and the method comprises the steps: determining neutron flow beams corresponding to each target depth, and carrying out a cell survival experiment based on a cell survival experiment device through employing the neutron flow beams corresponding to the target depths for different target depths, thereby obtaining the cell survival score model based on the cell survival score model. Obtaining a plurality of groups of fitting sample pairs under the target depth; and fitting model parameters in a cell survival score initial model by using the fitting sample pair under each target depth, so as to obtain a cell survival score model corresponding to each target depth, according to the method, the cell survival score models suitable for different target depths can be rapidly obtained, the obtaining efficiency of the models of different target depths is improved, the models are solved by utilizing multiple groups of fitting sample pairs, and the model accuracy of the cell survival score models is also effectively improved.

The invention provides a multi-nuclide radioactive activity concentration detection method, system and device and a storage medium, and relates to the technical field of radioactive solid waste detection. The detection method comprises the following steps: acquiring attribute information of a to-be-detected sample; obtaining a detection result; acquiring activity proportions of various nuclides; based on the activity proportion of each type of nuclide, determining the activity proportion of each type of nuclide easy to measure and a scale factor between each type of nuclide difficult to measure and the nuclide easy to measure; based on the material type, the volume and the density of the to-be-detected sample, determining the detection efficiency corresponding to each type of easily-detected nuclide; and determining the radioactive activity concentration of each type of nuclide based on the quality of the sample to be detected, the detection result, the detection efficiency of each type of easy-to-detect nuclide, the activity proportion of each type of easy-to-detect nuclide and the scale factor between each type of difficult-to-detect nuclide and easy-to-detect nuclide. The radioactive activity concentration of the easily-detected nuclide in the sample to be detected and the radioactive activity concentration of the difficultly-detected nuclide which cannot be effectively detected by detection equipment are accurately obtained, and high-sensitivity detection and evaluation of the sample to be detected are realized.

The invention relates to a full-automatic test system and method compatible with multi-type component irradiation tests, and the system comprises an irradiation main control board, an irradiation test board and an irradiation load board which are disposed in an irradiation room and are connected through a cable, and an electronic load, a programmable power supply, an upper computer and a digital oscilloscope which are disposed in a test preparation room. The system can compatibly support the irradiation test of the total dose effect and the single event effect, is suitable for the rapid assessment demand of multiple types of COTS components on a large scale, and can meet the urgent demand of the commercial spaceflight field for the evaluation of the radiation resistance of the COTS components.