130 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 invention relates to a nuclear main pump lead-bismuth lubrication guide bearing structure for negative feedback regulation, and belongs to the technical field of systems of nuclear energy, high-temperature industry, energy and chemical industry, scientific research and the like. The bearing structure is internally provided with an even number of cylindrical pipelines and spiral pipelines which are circumferentially arranged, the inner wall of the bearing structure is sequentially provided with a feedback cavity, a high-pressure liquid tank, a liquid return tank and a working cavity in the axial direction, and the two ends of the spiral pipelines are connected with the feedback cavity and the working cavity respectively. The bearing capacity of the lead-bismuth lubrication guide bearing of the nuclear main pump is improved, the leakage problem is solved, and the lead-bismuth lubrication guide bearing is suitable for aerospace vehicle propulsion systems, ocean engineering deep sea equipment and the like.

The invention discloses a high-temperature liquid environment impact-tangential multi-mode fretting wear test method and device. The device comprises an optical platform, a gas supply device, and an impact loading mechanism, a tangential movement mechanism, a test kettle, a test crucible and a liquid storage kettle which are mounted on the optical platform, the impact loading mechanism comprises an impact loading voice coil motor module, an impact shaft and an impact shaft supporting assembly; the tangential movement mechanism comprises a tangential movement voice coil motor module, a tangential shaft and a tangential shaft supporting assembly; and a test kettle cover and a liquid storage kettle cover are respectively arranged on the test kettle and the liquid storage kettle. According to the testing machine, various contact modes can be tested, the displacement adjustable range of the impact loading module and the tangential motion module is larger than that of an existing testing machine in the industry, the testing mode can cover the micro-motion and sliding range, and the application range is wider; various liquid environments such as liquid lead bismuth and water in the nuclear power field can be simulated, and meanwhile the temperature and the oxygen content in the environments can be regulated and controlled.

The invention provides an electric contact type liquid level meter and a manufacturing method thereof. The electric contact type liquid level meter is used for detecting the liquid level height of liquid lead bismuth in a container and comprises a liquid level meter body, a stainless steel cylindrical table, a plurality of insulating electrode columns and a plurality of adjustable locking pieces. A mounting hole is formed in the liquid level meter main body; the stainless steel cylindrical table is located in the mounting hole and fixedly connected with the liquid level meter body in a sealed mode, and a plurality of avoiding through holes are formed in the stainless steel cylindrical table; each insulating electrode column comprises an adjusting part, a connecting part and a detecting part which are connected in sequence, and the connecting part of each insulating electrode column is arranged in the corresponding avoiding through hole in a penetrating manner and is fixedly connected with the hole wall of the avoiding through hole in a sealing manner; the lengths of the detection parts of the plurality of insulated electrode columns are different; the adjustable locking piece is movably connected with the adjusting part and abuts against the second end face of the stainless steel cylindrical table. The electric contact type liquid level meter not only has better applicability, but also has better use stability.

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 relates to a fatigue life prediction method based on a physical failure mechanism in a liquid lead bismuth environment, and the method comprises the following steps: building a representative volume element model, and defining elements belonging to a slip band; defining a crystal plasticity constitutive equation; determining parameters in the crystal plasticity constitutive equation; calculating the average shear strain range of the slip band; carrying out a fracture toughness test to obtain specific fracture energy; establishing a fatigue life prediction model based on a physical failure mechanism; carrying out a symmetrically cyclic low-cycle fatigue test on the metal material in a predicted-temperature high-oxygen liquid lead bismuth environment to determine the thickness of an oxide film; and establishing a fatigue life prediction model in the high-oxygen-concentration liquid lead bismuth environment, and predicting the fatigue life of the metal material in the high-oxygen-concentration liquid lead bismuth environment. According to the method, the fatigue life in the liquid lead-bismuth environment can be predicted by carrying out a low-cycle fatigue test for calibrating crystal plasticity constitutive equation parameters in the air at the predicted temperature and a fracture toughness test in the air and liquid lead-bismuth environment.

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 discloses a temperature measuring device for measuring the center temperature of a lead bismuth alloy heating section pipeline. The temperature measuring device comprises a supporting pipe, a thermocouple and a guide rod, the supporting pipe penetrates through the interior of the heating section pipeline body in the radial direction, a first through hole and a second through hole are formed in the connecting positions of the supporting pipe and the pipe walls of the left side and the right side of the pipeline body, and a detection window is formed in the middle of the supporting pipe. The thermocouple and the guide rod are in sealed connection with the pipeline body, one end of the thermocouple is provided with a detection portion and a bending portion, one end of the guide rod is provided with a guide face, the end, provided with the detection portion, of the thermocouple extends into the supporting pipe from the first through hole, the end, provided with the guide face, of the guide rod extends into the supporting pipe from the second through hole, and the guide face abuts against the bending portion. And the bending part is formed, so that the detection part extends out of the detection window. The temperature measuring device is convenient to install, high in measuring precision, resistant to high temperature and corrosion and suitable for the working environment of the liquid lead bismuth alloy.

The invention belongs to the technical field of nuclear thermal hydraulic power, and particularly relates to a three-dimensional lead-based cold micro reactor integrated thermal hydraulic calculation method based on UDF development. Comprising the following steps: developing thermophysical property modules of density, constant pressure specific heat capacity, heat conductivity and viscosity of coolant lead / lead bismuth; determining a numerical value of a turbulence Prandtt number Prt in the turbulence model; obtaining a viscous resistance coefficient and an inertial resistance coefficient of the porous medium model of the single-box fuel assembly; acquiring a viscous resistance coefficient and an inertial resistance coefficient of the porous medium model of the main heat exchanger; cFD numerical simulation calculation is carried out; the lead-based cold micro reactor is subjected to integrated modeling, and a reactor core, a pump channel, a main heat exchanger and a coolant flow channel are simplified. The method has the beneficial effects that by developing and calling the UDF of the physical property module and the turbulent flow Prandtt number calculation module, the physical property parameters of the liquid metal lead in the flowing process and the change of the turbulent flow heat conductivity in the turbulent flow model can be more accurately simulated.

The invention discloses a multi-element high-activity element coating for forming a self-repairing Al2O3 protective layer in a non-oxygen-control lead bismuth alloy and a preparation method of the multi-element high-activity element coating. The method comprises the following steps: 1, carrying out pre-grinding and polishing treatment on the surface of a matrix, and then carrying out ultrasonic cleaning and drying; (2) embedding in powder containing Al and Cr, and sealing; 3, placing in a heating furnace, and filling protective gas for heating and heat preservation; 4, soaking in liquid lead-bismuth alloy; and 5, cleaning and drying. According to the method, high-activity elements Al and Cr are introduced by adopting a powder burying and heating method, an Al2O3 oxide layer is formed by combining a liquid lead-bismuth alloy soaking method to serve as a diffusion barrier, dissolved oxygen and Pb-Bi are prevented from invading into a crystal boundary, alloy elements are prevented from being dissolved and leached into LBE, the effect of isolating liquid metal from a metal matrix is achieved, oxidation corrosion is prevented from being further generated, and the service life of the LBE is prolonged. The corrosion protection method is suitable for the fields of nuclear corrosion, liquid metal corrosion, corrosion protection of nuclear reactor structure materials and the like.

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 invention discloses a preparation method of a steel wire rope for testing. The preparation method is specifically implemented according to the following steps: step 1, preparing a lead-bismuth alloy; 2, a steel wire rope with the length not smaller than 1 m is cut out; step 3, removing the head of the cut steel wire rope; 4, grease on the detached rope head is cleaned, and moisture is removed in an air-drying mode; and 5, the lead bismuth alloy is used for casting the rope head. According to the preparation method of the steel wire rope for testing, the steel wire rope head can be manufactured by a hot casting method, the reliable consolidation of a casting material to the steel wire rope is ensured, the casting temperature is effectively reduced to 200 DEG C or below, the influence of the thermal action on the performance of the steel wire rope is eliminated, the casting material can be more efficiently recycled, and the energy consumption is effectively reduced.

The invention discloses a performance evaluation device and method for a Po trapping material, and relates to the technical field of radioactive waste gas treatment.The device comprises a gas pipeline, the gas inlet end of the gas pipeline is connected with a flow control valve, the rear end of the flow control valve is connected with a gas preheater, and the rear end of the gas preheater is connected with a high-temperature heating furnace; the rear end of the high-temperature heating furnace is connected with a gas refrigerator, the rear end of the gas refrigerator is connected with a thermometer, the rear end of the thermometer is connected with a Po trapping material detection structure, and the rear end of the Po trapping material detection structure is connected with a pipeline pressure control structure; a gas pipeline between the gas preheater and the high-temperature heating furnace is connected with a branch pipe; and the branch pipe is connected with a liquid lead bismuth propelling structure. The evaluation of the Po-210 trapping performance of the trapping filter material under different temperature working conditions can be realized, a performance verification method of the Po-210 trapping filter material and even a Po-210 trap can be supported, and quantifiable trapping efficiency is provided.

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.

The invention discloses a loop type oxygen concentration sensor for a liquid lead bismuth circulation loop, which is characterized in that the lower end of a concentrated positive electrode lead is inserted into a reference electrode, and the reference electrode is fixed with a straight-through clamping sleeve; the positive electrode lead is arranged in the center of the electrode side protection steel sleeve, the electrode side protection steel sleeve and the straight-through side protection steel sleeve are connected with the reducing clamping sleeve through threads from the upper portion and the lower portion respectively, and the lower end of the electrode side protection steel sleeve is connected with the straight-through clamping sleeve through threads. Solid oxide electrolyte is arranged in the electrode side protection steel sleeve, and an insulating sleeve is arranged in the straight-through side protection steel sleeve. Compared with a common loop type oxygen concentration sensor, the liquid lead bismuth oxygen concentration sensor is more suitable for directly measuring the oxygen concentration at a pipeline in a liquid lead bismuth circulation loop. The reference electrode adopts LSCF powder, and in previous tests, the lowest working temperature is 200 DEG C, so that various requirements are met.

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.