28 results about "Nuclear material" patented technology

According to the ventilation system of the nuclear material production line and the nuclear material production line workshop, air exhaust equipment and air supply equipment in the system are used for conveying fresh air to a sealed area outside a target area, and the target area is the sealed area with the highest risk level; the air supply equipment is further used for extracting air from the adjacent sealing area with the risk grade lower than that of the target area and conveying the air into the target area so as to form directional airflow flowing from the low-risk area to the high-risk area. And the exhaust equipment is used for exhausting air in each sealing area. The control device is electrically connected with the air supply equipment and the air exhaust equipment and used for adjusting the air supply amount and the air exhaust amount of all the sealing areas so that the negative pressure gradient can be maintained among the multiple sealing areas, and the negative pressure in the target area is higher than the negative pressure in the adjacent sealing areas. The ventilation system can effectively avoid radioactive aerosol leakage in a high-risk area.

The invention discloses a reactor nuclear material cross-scale simulation method coupling microstructure simulation and mechanical-thermal performance calculation. The method comprises the following steps: a, planning a most unit sampling point through a most unit method; b, simulating through a mesoscale phase field model to obtain force thermal parameters; c, the force and heat parameters are input into a finite element model to be simulated to obtain force and heat performance; d, the mechanical and thermal performance is input into the phase field model for simulation to obtain the structure morphology of the target nuclear material; e, obtaining a macroscopic scale-mesoscopic scale coupling model by circulating the step c and the step d; f, obtaining a strong coupling model through physical time axis control; and g, constructing a database of the relationship between the mechanical and thermal parameters and the mechanical and thermal performance through a data-driven neural network algorithm. According to the method, strong coupling is achieved through parameter transmission of the mesoscale phase field model and the macroscale finite element, the macroscale and the mesoscale are connected through the most element method, the parameter transmission precision can be adjusted according to convergence, and novel reactor material mechanical and thermal performance prediction can be achieved.

The invention belongs to the technical field of nuclear material measurement and analysis, and particularly relates to a neutron detection method for measuring the mass of a nuclear material and a radiation dose field of the nuclear material. According to the embodiment of the invention, the method comprises the steps: carrying out the energy response calculation and calibration of a detector through a parallel beam standard neutron source, and obtaining a calibration factor; performing energy response calculation and calibration on the detector by taking a to-be-measured object as a target object, determining the energy response and fluence-ambient dose equivalent conversion coefficient of the detector in a radiation field of the to-be-measured object, and realizing simultaneous measurement of a neutron counting rate, a fluence rate and an ambient dose equivalent rate; and the requirements of carrying out radiation dose field monitoring while carrying out quantitative analysis on the to-be-detected object in a special scene are met. The technical scheme of the invention can be popularized and applied to fixed-point monitoring of a to-be-detected system with known or measurable nuclear material source item composition and isotope abundance in nuclear facilities, or retention volume analysis and radiation dose measurement before transfer or treatment of some equipment for treating nuclear materials.

The utility model discloses a kind of material species correction measurement devices of passive nuclear material level meter, it is related to passive nuclear material level meter technical field, including material level meter body, the material level meter body one end is provided with adjusting mechanism, the adjusting mechanism includes lead screw sliding table assembly, support and bevel gear one, in the utility model, bevel gear two drives bevel gear one rotation, bevel gear one and crossbar synchronous rotation, the inclination angle of adjustable detector assembly, by motor one drive screw rotation, can drive connecting block along guide plate sliding, to change the use position of detector assembly, adjustment detector assembly received effective radiation amount, compensate the absorption difference of different material species, complete material species correction measurement, satisfy the requirement of precision and stability to industrial production, the installation bolt in limit block can limit installation ring, improve the stability when using built-in component, also convenient for installation ring and built-in component installation and disassembly in the installation of positioning ring bottom.

The invention discloses a double-loop water chemical multi-parameter coordinated regulation and control test device for nuclear power material corrosion simulation. The double-loop water chemical multi-parameter coordinated regulation and control test device comprises a low-pressure water chemical pretreatment loop, a high-temperature and high-pressure corrosion simulation loop and a control module, the low-pressure water chemical pretreatment loop is connected with the high-temperature and high-pressure corrosion simulation loop through a pipeline and a valve, so that the test medium regulated and controlled by the low-pressure water chemical pretreatment loop is conveyed to the high-temperature and high-pressure corrosion simulation loop and flows back to the low-pressure water chemical pretreatment loop; the control module is electrically connected with the first monitoring component, the second monitoring component, the dissolved hydrogen / oxygen control unit, the dosing unit and the autoclave heating unit, receives and analyzes the hydrochemical parameter deviation of the low-pressure hydrochemical pretreatment loop and the high-temperature and high-pressure corrosion simulation loop by adopting a PID (Proportion Integration Differentiation) regulation algorithm, and dynamically regulates the working state of the execution unit; therefore, multi-parameter coordinated regulation and control are realized.

The application discloses a method for calculating the upper limit of impurity content of nuclear materials of a fusion device, and is used for analyzing the impurity control requirement of materials serving in the nuclear environment of the fusion device. The method is characterized in that: under the service environment conditions and examination requirements of the specified nuclear materials, the main components and the possible impurity elements contained in the materials are simulated, and the control requirement of the impurity elements is determined according to the nuclear response calculation of various normalization indexes. The method can realize the rapid calculation of the upper limit of impurity content of the nuclear materials of the fusion device under the service conditions, and can be applied to the design analysis of the nuclear materials of the fusion device and the fusion device.

The invention relates to the technical field of nuclear material analysis, in particular to a plutonium solution specific activity determination method and application, and the plutonium solution specific activity determination method comprises the following steps: taking a plutonium solution with known specific activity A1 as a standard solution, determining the liquid flash counting rate of the standard solution, and recording the liquid flash counting rate as C1; obtaining a second-order conductance spectrum of the standard solution by using an ultraviolet-visible absorption spectrum method, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the standard solution, and recording the peak area as S1; measuring the liquid flash counting rate of the to-be-measured solution, and recording the liquid flash counting rate as C2; obtaining a second-order conductance spectrum of the to-be-detected solution by using an ultraviolet-visible absorption spectrometry, determining the peak area of a characteristic absorption peak of tetravalent plutonium in the second-order conductance spectrum of the to-be-detected solution, and recording the peak area as S2; and calculating the specific activity A2 of the solution to be detected according to the following formula. According to the method, liquid scintillation counting and ultraviolet-visible spectrophotometry are combined, so that combination of activity response and concentration response is realized, and acquisition of isotope composition of a plutonium solution to be detected and complex sample pretreatment are not needed.

The invention belongs to the field of nuclear materials, and particularly relates to a nuclear fuel and a preparation method thereof and a reactor, the nuclear fuel comprises a nitride matrix and an MAX phase material distributed in the nitride matrix; the chemical formula of the MAX phase material is Mn + 1AXn, M is selected from at least one of Ti and Cr, A is selected from at least one of Si and Al, X is selected from C, and n is 1 or 2. According to the nuclear fuel disclosed by the invention, the MAX phase material is introduced into the nitride matrix, and a corrosion-resistant oxide layer is generated in situ by utilizing the MAX phase material to block water permeation, so that the nuclear fuel has the properties of high thermal conductivity, relatively strong water corrosion resistance, steam oxidation resistance and radiation resistance, and can be applied to a light water reactor; the application risk of the existing uranium nitride fuel in the light-water reactor is reduced, and the safety and economy of the reactor are improved.

The invention relates to a nuclear material warehouse abnormity early warning system and method, and the system comprises a laser radar personnel tracking system, a nuclear radiation detection network system, and an ultra wide band wireless positioning system, each system employs a layered architecture, and is composed of a sensing layer, a network layer, a processing layer, and an application layer, in the sensing layer, the laser radar personnel tracking system is provided with a plurality of laser radars, the nuclear radiation detection network system is provided with radiation detectors distributed in a place, and the ultra-wideband wireless positioning system is provided with an ultra-wideband tag and an ultra-wideband base station antenna which are arranged on a nuclear material container; the network layer is provided with equipment responsible for data transmission and communication of each system sensor; the processing layer is provided with a processor for carrying out processing, feature extraction and information fusion on data of each system sensor; and the application layer realizes anomaly detection, early warning and visual display. According to the invention, identification of illegal behaviors of personnel and early warning and positioning of illegal transfer of nuclear materials based on multi-sensing information fusion are realized, and the intelligent detection and identification capability of nuclear security is significantly improved.

The invention provides a quality measurement method, a model training method, electronic equipment, a storage medium and a program product. The method comprises: obtaining neutron counting data of a nuclear material to be measured within a first measurement duration, the first measurement duration being less than a second measurement duration, and the second measurement duration being a duration for performing neutron multiplex measurement on the nuclear material to be measured based on a preset mathematical model; based on the neutron counting data, a neural network model is used for conducting mass measurement on the to-be-measured nuclear material, a measurement result output by the neural network model is obtained, and the measurement result represents the mass of the to-be-measured nuclear material. By means of the scheme, the accuracy of nuclear material quality measurement can be improved under the condition that the measurement time of the to-be-measured nuclear material is shortened.

Described herein, are methods for providing a protective coating to a storage container for storing nuclear material, the method comprising depositing nickel particles on at least one surface of the substrate to produce the protective coating, wherein the nickel particles are deposited by cold spraying a composition comprising nickel particles and a carrier gas comprising nitrogen. In one aspect, the carrier gas consists essentially or consists only of nitrogen. The methods do not require pretreatment or modification of the nickel particles prior to cold spraying, which makes the methods described herein economically practical. The coatings produced by the methods described herein possess several advantageous properties including, but not limited to, high adhesion strength to the storage system and low porosity. The coatings produced by the methods described herein are effective against chemical attack such as, for example, CISCC.

The invention provides an electronic seal assembly, an electronic seal automatic sealing management system and an automatic sealing management method. The method comprises the following steps: setting an electronic seal to record traceability information and an on-off state of a nuclear material container; an on-off locking assembly is arranged to be connected to an installation position of the electronic seal, the electronic seal is connected in the state that the nuclear material container is locked, and the electronic seal is disconnected in the state that the nuclear material container is loosened, so that the storage information and the storage state of the nuclear material can be automatically supervised, the harm of the nuclear material to workers is reduced, and the working efficiency is improved. And the sealing state of the nuclear material container is monitored in real time, stability and reliability are achieved, manual stocktaking is not needed, and the management efficiency is improved.

The invention relates to the technical field of alloy materials, and provides a FeCrV-series low-activation high-strength high-entropy alloy and a preparation method and application thereof. The general formula of the alloy is represented by FeCrVTaxWyTiz, wherein 0 lt; x is less than or equal to 0.2, 0lt; y < = 0.2, 0 < = z < = 0.4. The room-temperature mechanical property of the high-entropy alloy is emphatically optimized, the yield strength of the designed alloy at the room temperature is higher than 1370 MPa, and the plastic deformation exceeds 3.3%. Compared with an existing low-activation high-entropy alloy, the low-activation high-entropy alloy has the advantages of being excellent in comprehensive performance and low in cost. The material can be used as a nuclear material of a fusion reactor and a new generation fission reactor, solves the problems of high cost, insufficient mechanical properties and the like of a traditional low-activation nuclear material, and further promotes the application and development of nuclear energy in the fields of aviation, national defense and the like.

The present application relates to a kind of spent fuel insoluble residue processing and analysis method, comprising extracting residue, drying and weighing, strengthening dissolution, analyzing residue heavy uranium plutonium content and the like steps;Among them, through blank filter membrane contrast and eluent double baseline control, the interference influence of the filtration process in residue analysis is significantly reduced, so that nuclear material weighing result is more quantitative and reliable, conservative and reliable.Through in small sample amount, high radiation, complex multiphase matrix condition, using optimized mixed acid system proportioning and reaction time / temperature window, the full dissolution of trace target nuclide uranium / plutonium is realized, the purpose of quantitative analysis of target nuclide in high radioactivity residue is achieved, to ensure the accurate determination and safe and efficient processing of target nuclide in residue.The present application will soluble nuclide be transferred into liquid phase as far as possible, the source item intensity and volume of high-level solid residue are reduced to the greatest extent, the burden of final radioactive waste disposal is reduced, and it is suitable for insoluble residue component analysis in nuclear fuel reprocessing plant.

Moderated nuclear reactors are disclosed. Hydrided moderator materials may be used to reduce fuel mass and costs. The reactor designs may be based on a unit geometry that includes a combination of fuel that includes nuclear material, moderator(s) that moderate neutrons, and heat pipes for thermal heat removal. The nuclear reactors may have a snowflake geometry or an opal geometry, for example. Low enrichment fuel of less than or equal to 19.75% may be used.

This invention discloses a cross-scale simulation method for reactor nuclear materials that couples microstructure simulation with mechanothermal performance calculation. The method includes: a) planning the most optimal element sampling points using the minimum element method; b) simulating mechanothermal parameters using a mesoscale phase-field model; c) inputting the mechanothermal parameters into a finite element model to simulate mechanothermal performance; d) inputting the mechanothermal performance into a phase-field model to simulate the microstructure of the target nuclear material; e) obtaining a macroscale-mesoscale coupled model by iterating through steps c and d; f) obtaining a strongly coupled model through physical time axis control; and g) constructing a database of the relationship between mechanothermal parameters and mechanothermal performance using a data-driven neural network algorithm. This invention achieves strong coupling through parameter transfer between the mesoscale phase-field model and the macroscale finite element method, connects the macroscale and mesoscale using the minimum element method, and allows for parameter transfer accuracy adjustment based on convergence, enabling the prediction of the mechanothermal performance of novel reactor materials.

The proposed invention relates to a system and method for estimating the concentration of a nuclear material present in a molten salt, and may estimate the concentration of a nuclear material accurately and with high reliability at low cost using the in temperature change difference that appears as the salt cools among components present in the molten salt in a molten salt reactor.

The application discloses a passive nuclear material level meter, a material level output control method thereof during nuclear radiation detection, and a monitoring system. The material level output method comprises the following steps: determining whether there is a nuclear radiation detection interference in a measurement environment of the passive nuclear material level meter; and performing at least one of the following output guarantee operations: setting an output switch of the passive nuclear material level meter to a preset guarantee state, wherein the preset guarantee state is an on state or an off state of the switch; or maintaining the output switch of the passive nuclear material level meter in a switch state before the determination that there is the nuclear radiation detection interference; or replacing a normal material level value of the passive nuclear material level meter with a replacement material level value, or determining a switch state of the output switch of the passive nuclear material level meter based on the replacement material level value, wherein the replacement material level value is used to replace the normal material level value when the detection interference is detected, and the normal material level value is a material level value generated based on real-time measurement data in a state without performing the guarantee operation. The application realizes the guarantee control of the material level output during the nuclear radiation detection.

The present application belongs to the technical field of nuclear material retention amount measurement and analysis, and particularly relates to a detection efficiency correction method for nuclear material retention amount analysis and a detector, wherein the method comprises the following steps: step S1, establishing a mathematical model suitable for a detection object; step S2, obtaining an environmental background and a gamma energy spectrum of the detection object; step S3, analyzing a full-energy peak area of characteristic gamma rays in the gamma energy spectrum; step S4, deducting the contribution of the environmental background to obtain a count rate of characteristic gamma rays of the nuclear material retention amount; step S5, determining intrinsic detection efficiency; step S6, determining geometric detection efficiency; step S7, performing decay absorption efficiency correction to obtain a decay correction parameter; and step S8, introducing the decay correction parameter to calculate the nuclear material retention amount.

The application discloses a high-temperature and high-pressure multi-mode abrasion test device, which comprises a rack and a high-pressure kettle body for arranging a sample. A cover body with a lifting assembly is arranged on the top of the high-pressure kettle, and a Z-axis normal loading assembly is arranged on the top of the cover body, so that a normal load can be applied to the sample. An X-axis sliding loading assembly and a Y-axis impact loading assembly are arranged on the side of the high-pressure kettle, and the two assemblies are arranged vertically and non-coplanarly, and can realize horizontal sliding and impact motion loading of the sample. The rack is also integrated with a water circulation system and a steam circulation system, which are both connected with the inside of the high-pressure kettle. The water circulation system can form a high-temperature and high-pressure water environment, and the steam circulation system can form a controllable high-temperature steam environment. The device can accurately simulate the complex fretting conditions of nuclear materials under the conditions of high-pressure water and high-temperature steam, and can simultaneously bear sliding, impact and normal loads, so that the complex service scene of nuclear power key components can be truly restored, the abrasion behavior of the materials can be effectively characterized, the failure mechanism can be clarified, and reliable test support can be provided for the performance research and safety analysis of nuclear power materials.

The invention discloses a nuclear critical event real-time monitoring recording and pre-alarm system and method. The system comprises a neutron-gamma composite solid optical fiber detector, an optical fiber transmission unit, a photoelectric converter, a charge sensitive preamplifier, a pulse amplification and high-speed sampling module, an ultra-wide dose monitoring module, a neutron-gamma separation module, a data processing and analyzing unit and a display and alarm unit. The method comprises the following steps: simultaneously collecting spontaneous fission neutrons and gamma generated in a nuclear material and neutrons and gamma in a regional environment, stably transmitting the collected fluorescence to a photoelectric converter at the rear end, and transmitting the fluorescence to a data processing and analyzing unit; analyzing the morphological characteristics of the critical event signal, and identifying a nuclear critical event; and displaying the monitoring result in real time and sending out an alarm signal under a preset condition. The system has the real functions of nuclear critical event identification, early warning, recording and return visit, the monitoring accuracy and timeliness are good, and the dynamic adaptive capacity and the advancement of nuclear critical event alarm are improved.

The invention discloses a nuclear material production line diesel engine room safety level ventilation system and a control implementation method. A control device in the system is electrically connected with a diesel generator, air supply equipment, air exhaust equipment and shutter equipment and used for judging the state of the diesel generator and controlling starting and stopping of the air supply equipment and the air exhaust equipment according to the state of the diesel generator; and opening / closing of the air inlet, the air supply outlet and the exhaust outlet is controlled through the shutter equipment. The ventilation system of the diesel generator room can quickly respond to the ventilation requirement of the diesel generator.

The invention discloses a device and a method for testing clamping force of a grillwork spring of a post-irradiation fuel assembly, and relates to the technical field of post-irradiation mechanical property testing of radioactive nuclear materials, and the device comprises a grillwork fixing assembly which is used for fixing a grillwork sample and is arranged on a displacement module; the output end of the vertical displacement driving assembly is connected with the transverse insertion assembly, and the vertical displacement driving assembly is used for driving the transverse insertion assembly to move vertically; the transverse insertion assembly comprises a transverse insertion rod, and the transverse insertion rod can be inserted into a clamping groove of a grillwork sample; the range finder is used for measuring the vertical displacement of the transverse insertion rod; and the force sensor is used for detecting the downward pressure of the transverse insertion rod on the grillwork sample. According to the invention, the spring clamping force performance test is carried out on the irradiated fuel assembly grillwork, and the press-in elastic force of the spring is tested by using a press-in method, so that the elastic force displacement curve of the spring is obtained, and the grillwork spring clamping force performance of the irradiated fuel assembly is evaluated.

The invention relates to a method for preparing a refractory high-entropy alloy diffusion couple sample based on a duplex process, and belongs to the technical field of alloys. According to the method, an electric arc melting method is adopted for carrying out semi-melting processing on a diffusion couple bonding surface of the refractory high-entropy alloy, the purpose of eliminating interface holes is achieved by softening a diffusion couple interface by adjusting current, and good bonding of high-melting-point diffusion couple samples of the refractory high-entropy alloy and pre-diffusion of components are achieved; and then a high-vacuum heat treatment furnace is used for conducting high-temperature diffusion treatment on the sample, and large-gradient component diffusion of the refractory elements is achieved. The problems that the refractory high-entropy alloy diffusion couple is poor in interface bonding degree, sensitive to impurities and prone to precipitation phase are effectively solved, the prepared refractory high-entropy alloy diffusion couple is high in quality and low in cost, a gradient component interval with hundreds of micrometers of continuous changes can be achieved on a millimeter-scale sample, and the method is suitable for industrial production. The method is suitable for ion irradiation mechanism research in the field of nuclear materials.

A method for recovering plutonium from destructive analytical waste liquid of complex systems includes the following steps: S1: containing C2O4 2‑ Waste liquid containing SO4 was added to H2O2 solution. 2‑ and PO4 3‑ The waste liquid was treated with Fe(NO3)3 solution; the two solutions were combined and the acidity was adjusted to (7-8) mol / L; S2: Sodium nitrite was added to oxidize plutonium to plutonium(IV), and then plutonium was extracted from the aqueous phase at a certain ratio and acidity, followed by back-extraction at a certain ratio to obtain a plutonium solution; S3: The plutonium solution obtained in S2 was adjusted in valence and acidity, and plutonium was recovered by column separation. This invention can solve the problem of plutonium recovery from destructive analytical waste liquid containing complex anions during the nuclear fuel cycle, effectively reducing the loss of nuclear materials. The collected waste liquid was treated using a waste liquid pretreatment-extraction / back-extraction-column separation process, and the final plutonium recovery rate was greater than 90%.