92 results about "Lead bismuth" patented technology

The invention belongs to the technical field of research and development of fast neutron reactor jackets and structural materials, and particularly relates to a high-temperature-lead-bismuth-corrosion-resistant high-silicon-content ferrite / martensite steel ladle tube and a preparation method thereof. According to the mass percentage, the composition mainly comprises the following components: 0.16-0.24% of C; 0.4 to 0.8 percent of Mn; cr: 11.6% to 12.4%; 1.2 to 1.8 percent of W; 0.1 to 0.4 percent of Ta; 0.2 to 0.4 percent of V; 1.0%-1.8% of Si and Fe. The preparation method comprises the steps of vacuum induction and vacuum arc remelting. Carrying out homogenization treatment and forging; extruding and annealing; cold rolling and annealing; and performing normalizing and tempering treatment. Through an efficient short-flow process route and reasonable smelting, pipe machining deformation and heat treatment processes, the microscopic structure of the material is remarkably improved, then the mechanical property and high-temperature lead and bismuth corrosion resistance of the finished pipe are improved, and the use requirement of the lead and bismuth cooling fast reactor fuel assembly cladding material under the high-temperature working condition is met.

The application relates to a rectangular narrow-channel lead-bismuth alloy flow heat exchange experimental device and an experimental method. The application is used to solve the problem that the existing experimental device cannot meet the demand of the research on the flow heat exchange characteristics of lead-bismuth alloy in a rectangular narrow channel. The flow direction of the lead-bismuth alloy in the experimental section is from top to bottom. The inlet and outlet cylindrical chambers and the rectangular variable-diameter passage of the experimental section are fixed by welding and an external mechanical fixing device. The rectangular narrow channel is composed of stainless steel sheets. The inner side of the narrow side of the channel is supported and sealed by a first-stage stainless steel pad. The outer side is supported and fixed by a second-stage stainless steel fixing pad through bolt connection. The third-stage sealing is realized by smearing high-temperature-resistant sealing glue between the stainless steel pad, the bolt and the bolt gap. The rectangular narrow-channel sheet is heated by an indirect electric heating mode. The application is used for the flow heat exchange experiment of lead-bismuth alloy.

The invention relates to special-corrosion-resistant martensitic heat-resistant steel and a preparation method thereof, belongs to the technical field of nuclear heat-resistant steel, and solves the problems of poor oxidation corrosion resistance, low strength and poor impact toughness and plasticity of ferrite / martensitic steel in high-temperature liquid lead bismuth in the prior art. The heat-resistant steel comprises the following chemical components in percentage by mass: 0.10-0.13% of C; 0.9 to 1.4 percent of Si; mn: 0.5 to 0.7%; 8.5 to 9.0 percent of Cr; 0.4 to 0.6 percent of W; 0.7 to 0.8 percent of Mo; 0.25 to 0.40 percent of Ni; 0.15% to 0.20% of V; 0.05 to 0.07 percent of Nb; the content of N is 0.045 to 0.065 percent; compared with the prior art, the heat-resistant steel disclosed by the invention has the advantages that a compact Si-rich oxide layer is ensured to exist in the heat-resistant steel by increasing the content of Si, so that the high-temperature liquid lead / lead bismuth corrosion resistance of the material is improved; by adjusting the content of Mn, Cr, Ni, W, Mo and other elements, it is ensured that the material has a single martensite structure, the heat-resistant steel has good room-temperature and high-temperature mechanical properties at the same time, and the heat-resistant steel is suitable for lead-cooled fast reactor structural materials.

The invention discloses an oxygen concentration sensor coupled with temperature detection, and belongs to the technical field of oxygen concentration sensing, a temperature sensing module and a first signal quick connector form a temperature measuring unit, and the temperature sensing module is used for sensing a temperature signal when the temperature sensing module is immersed in liquid lead bismuth alloy; and temperature data are transmitted through the first signal quick connector. A Pt electrode, a positive electrode lead, a negative electrode connecting wire and a second signal quick connector form an electromotive force measuring unit which is used for sensing oxygen partial pressure difference between the liquid lead-bismuth alloy and a reference electrode when the YSZ ceramic tube is immersed in the liquid lead-bismuth alloy and transmitting electromotive force data through the second signal quick connector; and the measured temperature data and electromotive force data are synchronized, and the oxygen concentration is obtained through a Nernst equation.

The application discloses a kind of steel material for nuclear reactor and its preparation method and application.The steel material includes stainless steel matrix and the oxidation layer coated on the surface of the stainless steel matrix;The oxidation layer includes first oxidation layer and second oxidation layer;The first oxidation layer includes the mixed layer with spinel type crystal structure and corundum type crystal structure;The second oxidation layer includes corundum type crystal structure;The second oxidation layer is between the first oxidation layer and the stainless steel matrix.The steel material in the application is provided with oxidation layer on the stainless steel matrix, the oxidation layer contains spinel type crystal structure and corundum type crystal structure, the two kinds of crystal structure are uniform, continuous and dense, thereby blocking liquid lead bismuth from penetrating into crystal structure, so that the steel material has excellent lead bismuth corrosion resistance.In addition, the oxidation layer in the application has high bonding strength with the stainless steel matrix, and the bonding strength can reach more than 80MPa.

The invention relates to the technical field of lead-bismuth reactors, and particularly discloses a liquid lead-bismuth alloy thermal stripe oscillation experiment device and method. The device comprises an experiment loop, a gas protection loop, a data acquisition device and an integrated control module. According to the experimental loop, a magnetic pump is used for driving lead-bismuth fluid and an air cooler to realize cooling through a cold and hot double-loop structure, lead-bismuth jet flow with temperature difference is formed, and the lead-bismuth jet flow is mixed in a three-inlet experimental section to simulate a hot stripe oscillation phenomenon. The method comprises the steps of gas replacement, preheating, loop filling, temperature and flow rate regulation and control, data acquisition and the like. The device can truly simulate a lead bismuth alloy thermal stripe oscillation process, effectively prevents high-temperature oxidation, has a modular experimental section structure, can research thermal stress responses under different structures, and provides reliable experimental data for reactor safety design.

The invention belongs to the technical field of lead-bismuth reactors, and particularly relates to a lead-bismuth reactor control rod assembly positioning structure. The control rod cluster comprises an upper end positioning structure, a lower end positioning structure, a tuning fork type upper end plug and a tuning fork type lower end plug, the control rod cluster is located between the upper end positioning structure and the lower end positioning structure, the control rod cluster comprises 19 control rods, the upper end positioning structure is connected with the tuning fork type upper end plug in a matched mode, and the lower end positioning structure is connected with the tuning fork type lower end plug in a matched mode. The upper end positioning structure and the lower end positioning structure are located at the two ends of the control rod bundle and jointly achieve positioning of the control rod. On the basis of meeting the requirement of flow distribution uniformity of the control rod assembly coolant and overcoming transverse shaking of the control rod, the lead-bismuth coolant uniformly flows through the rod cluster type control rod and the transverse impact of the coolant on the control rod is reduced on the basis of realizing rapid assembly of the control rod assembly.

The utility model discloses a kind of thermocouple response time measuring devices, including measuring pipeline, vertical pipeline, electric heating equipment and fixture, one end of measuring pipeline is provided with import, the other end is provided with export, vertical pipeline is vertically set on measuring pipeline, and with the inside of measuring pipeline is communicated, electric heating wire is set on the outer surface of measuring pipeline and vertical pipeline, fixture is located at the top of measuring pipeline, and fixed plate is vertically slidably arranged on fixture;High thermal conductivity lead bismuth liquid is used as medium in the application, heat can be quickly transferred to thermocouple and armored sleeve, reduce the lag caused by sleeve thermal resistance, fit actual working condition, reduce the measurement deviation caused by medium thermal property difference;Electric heating equipment precision temperature control, cooperate with flowing lead bismuth liquid, both ensure that step temperature test is accurate, and simulate actual dynamic heat exchange, avoid the response time misjudgment caused by heat accumulation at sleeve under static state.

The invention provides a high-temperature liquid lead bismuth alloy energy conversion test system and a test method thereof, belongs to the field of lead-based fast reactor thermotechnical hydraulic safety technology and energy transport performance test, and solves the problem that test research on an energy conversion system of a small modular reactor is still lacked at present. The device comprises a liquid lead-bismuth alloy loop, an argon bottle, a vacuum pump, a water cooling loop and a temperature sensor assembly, a vapor chamber in the liquid lead-bismuth alloy loop exchanges heat with a water cooling plate in the water cooling loop, and the argon bottle and the vacuum pump provide an inert environment for liquid lead-bismuth alloy and control the liquid level of a working medium in the liquid lead-bismuth alloy loop. The heat exchange capacity between the temperature equalizing plate and the water cooling plate under the specific working condition is obtained through the temperature collected by the temperature sensor assembly, the cooling water flow collected by the cooling water flow meter and the lead bismuth flow signal collected by the lead bismuth flow meter, and the energy mass transport characteristic of the liquid lead bismuth alloy loop is obtained. Therefore, the operation rule of the liquid lead-bismuth alloy energy conversion system is mastered.

This invention discloses a lead-bismuth high-heat transfer heat transfer device with rough elements arranged in a rectangular channel in the field of nuclear reaction heat transfer. From the desert side to the oasis side, it includes: a heating component with a rectangular flow channel structure inside, allowing liquid lead-bismuth alloy to pass through and heating the liquid lead-bismuth alloy inside; rough elements are arranged in the rectangular flow channel structure to simulate the actual flow channel environment; a feeding component connected to the feeding end of the heating component; and a discharging component connected to the discharging end of the heating component. The beneficial effects of this invention are: by setting rough elements on the inner wall of the flow channel plate to simulate the flow channel environment where liquid lead-bismuth alloy causes erosion and corrosion in the actual environment, the influence of flow channel roughness on the flow heat transfer characteristics of lead-bismuth alloy can be more accurately assessed. Furthermore, the modular design makes component replacement faster and the experimental efficiency higher.

The invention discloses a long-period high-flux high-temperature lead-bismuth corrosion test device, and relates to the technical field of lead-bismuth corrosion experiments.Sample rods of an annular array sample frame are evenly distributed around a stirring assembly in the circumferential direction, a modular clamp is arranged at the tail end of each sample rod, and a single clamp integrates multiple independent sample groove positions, so that a high-flux test is achieved; parallel corrosion tests of various materials and various working conditions can be completed in a single experiment, and compared with a traditional single-sample experiment, the material screening efficiency is greatly improved, and the experiment period is shortened; the corrosion behavior of the ODS-FeCrAl alloy under different doping proportions and different corrosion time is tested and analyzed under the oxygen control condition, the long-term service condition of a nuclear reactor structure material in a lead-bismuth coolant environment can be accurately simulated, and a reliable experimental basis is provided for corrosion resistance evaluation and service life prediction of the material.

This invention provides a method for preparing a high-performance potassium adsorbent for potassium extraction from seawater, belonging to the field of ion adsorbent technology. The present invention features a large potassium adsorption capacity, high ion exchange site density, and outstanding enrichment capacity for low-concentration potassium ions. It exhibits very low adsorption capacity for calcium and magnesium ions in the influent, precisely rejecting high concentrations of coexisting sodium, calcium, and magnesium ions, achieving exclusive adsorption only for potassium ions, resulting in high purity of the enriched product. It possesses a highly stable crystal framework structure resistant to acids and alkalis, improving the cycling stability of the potassium adsorbent. The small crystal size is beneficial for increasing the adsorption capacity of the potassium adsorbent; due to the small crystal size, growth is more complete, with fewer crystal defects, which is conducive to improving selectivity and cycling stability. The three-stage calcination crystallization process allows different materials to undergo precise chemical reactions or crystal growth at different temperature stages, facilitating the acquisition of potassium adsorbent crystals with high adsorption capacity, high selectivity, and high cycling stability.

The invention belongs to the technical field of nuclear energy materials and surface engineering, and particularly relates to application of an MAX phase coating in a lead bismuth environment. The MAX phase coating is deposited on the surface of the structural material, so that the corrosion resistance and wear resistance of the steam generator can be remarkably improved. The result shows that under the conditions that the temperature is 450 DEG C, the normal load is 50N, the displacement amplitude is 75 microns, the vibration frequency is 25Hz and the cycle index is 106, a stable aluminum oxide oxidation layer and a compacted abrasive dust layer can be formed, so that the Ni element is effectively prevented from being dissolved, and the corrosion rate of a structural material is reduced; meanwhile, the abrasion depth of the structural material is reduced by 70% compared with that before protection, the structure is stable, the binding force is high, and the structural material is still kept complete and has no obvious peeling or failure phenomenon even in a long-cycle test.

The application provides an evaluation method of lead and bismuth corrosion-resistant material, and relates to the field of lead and bismuth corrosion-resistant material, which comprises the following steps: calculating the root mean square displacement and diffusion activation energy of each element in the sample material in liquid lead and bismuth alloy, and screening each element of the sample material based on preset conditions; calculating the density and distribution characteristics of each element of the sample material at the solid-liquid interface, evaluating the compactness of the oxide film based on the root mean square displacement and diffusion activation energy of the screened qualified elements, obtaining the structure of the oxide film according to the distribution characteristics, and obtaining the corrosion resistance of the oxide film based on the compactness of the oxide film; and calculating the depth and quantity of lead and bismuth alloy atoms invading the sample material, obtaining the difference of the lead and bismuth corrosion resistance of the sample material without the oxide film, and determining the composition and content of the lead and bismuth corrosion-resistant material based on the corrosion resistance of the oxide film. The application can screen the material composition with strong lead and bismuth corrosion resistance in a short time, and has the advantages of short time, low cost, high safety and wide screening range.

The present application relates to the field of fatigue test, in particular to a kind of tubular sample dynamic liquid lead bismuth alloy loop corrosion fatigue test device and use method.Tubular sample is installed between upper and lower base, the lower end of tubular sample is sequentially communicated with the through hole in lower base, liquid lead bismuth alloy inlet pipe, the upper end of tubular sample is sequentially communicated with the through hole in upper base, liquid lead bismuth alloy outlet pipe.Tubular sample outer paste thermocouple real-time monitoring and control liquid lead bismuth temperature, outer surface installation extensometer strain measurement.Liquid lead bismuth is driven by electromagnetic pump through storage tank, enters reaction kettle and is heated and oxygen is controlled, after flow rate is measured by flowmeter, it flows into tubular sample, then backflow to storage tank and forms loop.The outer wall of loop pipeline is equipped with armored electric heating and thermal insulation cotton, to ensure temperature control.The present application realizes the accurate control of high-temperature liquid lead bismuth temperature, dissolved oxygen and flow rate, supports dynamic strain control fatigue test, and evaluates the corrosion fatigue performance of material in flowing high-temperature liquid lead bismuth environment.

The application discloses an experimental testing device and a testing method suitable for high-temperature lead-bismuth erosion, and belongs to the technical field of nuclear energy experimental testing devices. The device comprises a variable frequency motor, a motor support, a main shaft, a stuffing box, a shaft seat, a flange cover, a tank body, a mounting base, a test piece disc and a medium rotation prevention device. The output shaft of the variable frequency motor penetrates through the top cover of the motor support, the upper end of the main shaft is connected with the output shaft of the variable frequency motor through an elastic column pin coupling, and the stuffing box and the shaft seat are sleeved on the outside of the main shaft. The lower part of the motor support is detachably connected with the shaft seat, the shaft seat is detachably connected with the top of the flange cover, the flange cover is detachably connected with the top of the tank body, and the tank body is welded on the mounting base. The lower end of the main shaft extends into the tank body, and three test piece discs are arranged at equal intervals in the tank body, and test pieces are detachably installed on the test piece discs. The medium rotation prevention device is embedded in the tank body. The top edge of the tank body is connected with a protective gas inlet and a protective gas outlet, and the bottom is provided with a lead-bismuth medium inlet and outlet.

A metal hydride fuel burn-up self-sustaining reactor core controlled by burnable poison relates to the technical field of nuclear reactor cores, and comprises a low-enrichment-degree control rod-free fuel assembly located in the center of the reactor core, and a middle-enrichment-degree control rod-free fuel assembly arranged around the periphery of the low-enrichment-degree control rod-free fuel assembly. A middle-enrichment-degree safety rod-containing fuel assembly is arranged between the fuel tank and the fuel tank; a high-enrichment-degree control rod-free fuel assembly is arranged around the periphery of the medium-enrichment-degree control rod-free fuel assembly, and a medium-enrichment-degree compensation adjusting rod-containing fuel assembly is arranged between the medium-enrichment-degree control rod-free fuel assembly and the high-enrichment-degree control rod-free The periphery of the high-enrichment-degree control rod-free fuel assembly is filled with lead bismuth; the reactor core is used for solving the problem that a traditional reactor core is difficult to reach expected burnup depth and even causes short service life.

The invention discloses a method for optimizing a lead-bismuth venturi flow meter with ferroferric oxide particle deposition intervened by a magnetic field. The method comprises the following optimization steps: constructing a parameterized three-dimensional geometric model of the venturi flow meter; performing grid division on the model in computational fluid dynamics (CFD) software, and setting a multiphase flow model and a discrete phase model; compiling UDF for dynamically applying a virtual magnetic field in the flow field area of the tapered fillet section in the CFD solving process; the UDF is loaded, the virtual magnetic field serves as a source item to be coupled to a control equation of the fluid and the particle phase, and the influence of the virtual magnetic field on the particle motion trail is simulated; obtaining and analyzing the motion trail of the particles and the particle deposition amount of the fillet transition structure; based on an analysis result, adjusting the next one or more optimization variables and iteratively executing the steps until the particle deposition amount meets a preset requirement; according to the method, a virtual magnetic field which can be flexibly regulated and controlled is introduced by embedding a user-defined function, and an efficient simulation tool and a theoretical basis are provided for collaborative optimization of a flowmeter structure and a deposition suppression strategy.

The application belongs to the field of sewage treatment, and specifically discloses a lead-bismuth smelting wastewater treatment method. The method comprises the following steps: (1) performing a sulfidation reaction on waste acid wastewater and desulfurization and denitrification wastewater with a sulfidation agent, and obtaining first filtrate through solid-liquid separation; (2) mixing the first filtrate with chlorine washing wastewater and silver preparation wastewater, and sequentially performing oxidation treatment, iron-based flocculation treatment, fluorine ion precipitation treatment and flocculation treatment, and obtaining second filtrate through solid-liquid separation; (3) adjusting the second filtrate to an alkaline condition, and sequentially performing thallium removal treatment, calcium ion precipitation treatment and secondary flocculation treatment, and obtaining purified filtrate through solid-liquid separation. The application combines modular treatment units with a collaborative process to construct an efficient and economical multi-medium wastewater treatment system.

The application is suitable for the field of nuclear power detection, and discloses a method and device for measuring the dissolved iron content in liquid lead bismuth, which comprises the following steps: S1, taking out the liquid lead bismuth and adding it into a test container, and heating the assembly to a set temperature; S2, injecting argon into the test container to remove other gases, and then inputting oxygen, and measuring the change of the dissolved oxygen concentration in the liquid lead bismuth through an oxygen detection sensor; S3, substituting the measured oxygen concentration change rate and the net oxygen addition rate into a differential equation to calculate the solubility product; and S4, deriving the dissolved iron content through the measured equilibrium oxygen concentration in the saturated iron and the solubility product obtained in step S3. The method for measuring the dissolved lead bismuth eutectic oxygen activity through the oxygen detection sensor is simple in operation, can quickly and accurately measure the dissolved iron content, and can keep the liquid metal system in a balanced state by adjusting the oxygen addition rate in the system, so that the experimental efficiency is higher.

The application relates to the technical field of valve control and discloses a lead-bismuth valve control device and a control method, the device comprising a moving unit and a control unit, the moving unit being detachably connected with a valve core through a connecting sleeve; the control unit comprising a data acquisition module, a data storage module and a controller, the controller estimating the opening and closing state of the valve through a mapping model based on the real-time driving device movement data and the stored historical correlation data, and outputting a control signal to drive the valve to move; after the valve reaches the target position, the moving unit can be automatically detached from the valve core, and dynamic correction and model updating can be carried out based on multiple data; the application also correspondingly provides a control method, and through the comprehensive scheme of redundant position monitoring, dynamic torque control and closed-loop feedback calibration, the problems of insufficient control precision, poor dynamic adaptability, large driving interference and low operation and maintenance efficiency of the traditional valve are solved.

This invention belongs to the technical field of corrosion-resistant alloy materials, specifically disclosing a refractory high-entropy alloy resistant to liquid lead-bismuth corrosion, a cladding material, and its preparation method. The refractory high-entropy alloy resistant to liquid lead-bismuth corrosion is composed of the following chemical elements: Nb 18–27 at.%; Mo 18–27 at.%; Ta 18–27 at.%; W 18–27 at.%; Cr 10–25 at.%; Si: 0–9 at.%; wherein the Si content is not zero. The cladding material is prepared by multi-target magnetron sputtering to prepare a refractory high-entropy alloy coating resistant to liquid lead-bismuth corrosion on the surface of a substrate. The doping of Cr and a small amount of Si in the refractory high-entropy alloy resistant to liquid lead-bismuth corrosion of this invention promotes the formation of a protective continuous Cr₂O₃ layer, preventing direct contact between the liquid lead-bismuth alloy and the coating material, thereby significantly improving the coating's resistance to liquid lead-bismuth alloy corrosion.

The invention discloses an efficient and compact heat exchanger core for liquid metal and supercritical CO2, relates to the technical field of heat exchange, and solves the problems that a traditional heat exchanger in the prior art is large in size and insufficient in pressure bearing capacity. The heat exchanger comprises a plurality of heat exchange units, hot plates are arranged in the heat exchange units, and at least one cold plate is arranged below the hot plates. The invention provides an efficient and compact heat exchanger core body using liquid metal and supercritical carbon dioxide, the liquid metal comprises but is not limited to liquid lead bismuth, potassium, sodium, potassium-sodium alloy and gallium, through differentiated flow channel design and optimized arrangement, the heat transfer amount of unit volume is increased, the enhanced heat transfer requirement is met, meanwhile, the LBE flow resistance and the blocking risk are reduced, and the heat exchange efficiency is improved. The flow property and the heat transfer efficiency are both considered, and the application requirements of lead-cooled fast reactors and other liquid metal / supercritical fluid coupling heat exchange systems are met.

The invention belongs to the technical field of lead-bismuth stack material irradiation, and particularly relates to a material irradiation test device suitable for a lead-bismuth medium environment. The lower end of a test section is welded to the upper end of a lower connector, the upper end of the test section is in sealed connection with an outer sleeve, the other end of the outer sleeve is welded to a flange piece, an air inlet pipe and an air outlet pipe are arranged in the outer sleeve, and an air outlet in the upper end of the test section is welded to the lower ends of the air inlet pipe and the air outlet pipe; welding and fixing are carried out at the penetrating outlet; the air inlet pipe and the air outlet pipe penetrate through the flange assembly and then are welded and sealed with the sealing head assembly; the lower end of the air inlet pipe penetrates through a capsule reserved air pipe channel in the test section and is inserted into the bottom of the test section. The device is used for carrying out a material temperature control irradiation test in a lead-bismuth reactor, the purpose of reducing the temperature of an irradiation sample can be achieved, it is guaranteed that a stainless steel irradiation device of a novel structure can be used in a lead-bismuth environment, and the safety of the irradiation device can be guaranteed.

The application provides a method for capturing gold in lead anode slime by antimony reinforced bismuth, and belongs to the technical field of resource comprehensive utilization; on the basis of capturing gold and silver by lead bismuth, antimony is added to reinforce the effect of capturing gold by bismuth; through theoretical calculation, antimony atoms doped on the surface of bismuth can enhance the adsorption strength of gold atoms, and reinforce the effect of capturing gold by bismuth; therefore, the application develops a method for mixing lead anode slime, crude lead and crude antimony according to a certain proportion to obtain noble lead through reduction smelting, obtaining gold and silver alloy through oxidation and impurity removal of the noble lead, obtaining crude silver and crude gold through vacuum distillation of the gold and silver alloy, and obtaining high-purity silver and gold through electrolysis of the crude silver and the crude gold; compared with the method without adding crude antimony, the recovery rate of silver and gold is improved; by increasing the content of antimony in the noble lead, reducing the loss of gold in the reduction smelting process, and cooperatively smelting crude bismuth and crude antimony, the recovery rate of bismuth and antimony is improved, and efficient recovery and utilization of rare and precious metals in lead anode slime is realized.

The invention provides an impurity particle filtering device for a lead-bismuth loop, and belongs to the technical field of impurity filtering, the impurity particle filtering device comprises a barrel, a material conveying pipe and a conical shell, the material conveying pipe extends into the barrel and is communicated with the barrel, the conical shell is fixedly mounted at the bottom of the barrel, the barrel is communicated with the conical shell, and the conical shell is fixedly mounted at the bottom of the barrel. The conical shell is in a funnel shape, a flow guide plate is fixedly installed at the end, stretching into the barrel, of the conveying pipe, the flow guide plate inclines towards the end away from the conveying pipe, and the inner diameter of the barrel is larger than the inner diameter of the conveying pipe. Impurity particles and liquid lead-bismuth eutectic are separated and filtered on the basis of buoyancy applied to the impurity particles caused by density difference between the impurity particles and the liquid lead-bismuth eutectic, the device can run in a lead-bismuth circulation loop for a long time, and the impurity particles can be effectively filtered and stored in a barrel of a pressure container in real time; and the defects of high flow resistance, easiness in damage, easiness in blockage and the like caused by the existing filter are overcome.

The invention relates to the technical field of lead-bismuth reactor core flow distribution measurement, in particular to a lead-bismuth reactor core flow distribution test method. The method comprises the following steps: step 1, partitioning a reactor core of a lead-bismuth reactor; 2, calculating the Reynolds number of lead and bismuth in the lead-bismuth reactor core; 3, calculating the Reynolds number of water; step 4, determining that lead and bismuth in the lead-bismuth reactor core are equivalent to water; and 5, calculating a flow distribution factor. The reactor core flow distribution characteristic of the lead-bismuth reactor can be obtained under the test conditions of normal temperature and normal pressure, the reactor core flow distribution test device is suitable for reactor core flow distribution tests of liquid lead-bismuth reactors, liquid sodium reactors and other liquid metal reactors, the problem that tests cannot be carried out under the high-temperature environment is solved, and a theoretical basis is provided.

The invention relates to the technical field of valve control, and discloses a lead-bismuth valve control device and method.The device comprises an action unit and a control unit, and the action unit is detachably connected with a valve element through a connecting sleeve; the control unit comprises a data acquisition module, a data storage module and a controller, and the controller estimates the opening and closing state of the valve through a mapping model based on driving device motion data acquired in real time and stored historical associated data and outputs a control signal to drive the valve to act; after the valve reaches a target position, the action unit can be controlled to be automatically separated from the valve element, and dynamic correction and model updating are carried out based on multivariate data; the invention further provides a control method correspondingly, and through the comprehensive scheme of redundant position monitoring, dynamic torque control and closed-loop feedback calibration, the problems that a traditional valve is insufficient in control precision, poor in dynamic adaptability, large in driving interference and low in operation and maintenance efficiency are solved.

The application discloses a kind of lead bismuth and supercritical carbon dioxide heat exchanger break accident experimental system and method, the system includes lead storage tank, argon buffer tank, experimental container, high temperature and high pressure carbon dioxide storage tank, carbon dioxide storage tank and buffer tank and other auxiliary systems, specifically to simulate lead bismuth and supercritical carbon dioxide heat exchanger break accident under the temperature, pressure and bubble evolution, lead bismuth reactor loop extreme thermal hydraulic phenomenon caused;The whole experimental system is operated by different pipeline valve control loop, the pressure required by experiment is flexibly controlled using gas booster pump, different heating temperatures are obtained by adjusting heating wire power, different sizes and thicknesses of copper film are flexibly replaced to simulate heat exchanger break condition, temperature change and pressure response during supercritical carbon dioxide is discharged into lead bismuth in experimental container are monitored, and lead bismuth and supercritical carbon dioxide heat exchanger experimental data under initial different temperature and pressure are obtained.

The present application relates to circulating pump technical field, specifically to a kind of high-temperature liquid metal circulating pump damping device for nuclear industry, including base, the top of base is fixedly connected with driving device, driving device is fixedly connected with driving shaft, one side of driving device is provided with pump shell, pump shell is installed on base, the two ends of pump shell are communicated with inlet and outlet, the end of driving shaft away from driving device is fixedly connected with transmission gear two, the other side of transmission gear two is fixedly connected with pump shaft.The present application utilizes centrifugal force field generated by impeller rotation, so that the solid particles with higher density are automatically enriched to the inner wall of pump shell, through mechanical transmission mechanism, filter screen frame is driven to periodically expand and contract in specific area, through the unique design of bidirectional screw rod, the timing and period of filtration and backwashing can be accurately controlled, the source interception and efficient capture of lead bismuth alloy particles are realized, the vibration and wear of main pump are significantly reduced from the root, and the running stability and life are improved.