677results about "Reactors manufacture" patented technology

The invention relates to the technical field of fused salt purification, and provides a fused salt purification device and a fused salt purification method.The fused salt purification device comprises a heating furnace, heat insulation layers, a reactor, a sleeve, a gas inlet and outlet device and a crucible, the heating furnace is provided with multiple sections of heating areas in the height direction, and the heating areas are separated by the heat insulation layers and can independently control the temperature; the reactor is partially arranged in the heating furnace and extends into the multiple sections of heating areas, and the reactor is provided with a reaction cavity and a cavity opening communicated with the reaction cavity; the sleeve is placed in the reaction cavity from the cavity opening and covers the cavity opening, a placement cavity is formed in the sleeve, and the gas inlet and outlet device is communicated with the placement cavity and used for providing inert gas for the placement cavity; the crucible is placed in the containing cavity and used for containing the fused salt to be purified. After the to-be-purified fused salt is heated and melted, each section of heating area can be controlled from top to bottom to slowly cool, so that the fused salt is solidified from top to bottom, purification is completed, impurities flow to the bottom of the crucible, the upper-layer purified fused salt is obtained, and the structure is simple.

The invention discloses a method for preparing high-purity uranium carbide microspheres by a microfluidic-assisted internal gelation process, which comprises the following steps of: designing a uranium glue solution component containing carbon black to obtain a uranium glue solution which is stable for a long time at room temperature and quickly gelates at high temperature; the preparation method comprises the following steps: preparing gel microspheres with uniform size by using a uranium glue solution as a micro-fluidic dispersion phase through a micro-fluidic assisted inner gel process; the pore structure in the gel microspheres is maintained through washing and soaking with propylene glycol monomethyl ether, so that the crack-free gel microspheres are obtained; the UC nuclear fuel microspheres which are uniform in size, good in sphericity degree and high in phase purity are prepared through the carbon thermal reduction reaction of the non-cracking gel microspheres under the optimized sintering schedule, and development of ultrahigh-temperature gas cooled reactor nuclear fuel is expected to be promoted.

The invention discloses a prismatic TRISO particle dispersion additive fuel element as well as a preparation method and application thereof, and relates to the technical field of nuclear fuel. The method comprises the following steps: preparing the SiC shell by adopting a binder injection molding process or a photocuring molding process; the SiC shell is subjected to degreasing treatment; carrying out chemical vapor infiltration pretreatment on the SiC shell subjected to degreasing treatment; the pretreated SiC shell is filled with simulated TRISO particles and SiC matrix powder, high-solid-content SiC slurry is adopted for packaging, then an enhanced chemical vapor infiltration method is adopted for densifying the dried additive SiC element, and the prismatic TRISO particle dispersion additive fuel element is obtained. The TRISO fuel particles with high inherent safety and the nuclear-grade SiC ceramic material with excellent high-temperature resistance and irradiation resistance are combined, the additive manufacturing process is matched, the design flexibility and expansibility are improved, and the TRISO fuel particles have large application potential in the high-temperature gas cooled reactor.

The invention relates to a pressurized water reactor MOX fuel powder preparation method, which comprises: preparing a mixed actinide eutectic melt from a mixed actinide salt and a urea solid, and carrying out deamination, denitrification / decarbonization and reduction on the mixed actinide eutectic melt to directly obtain MOX fuel powder, the mixed actinide salt is hexavalent actinide nitrate and tetravalent actinide oxalate; when the mixed actinide salt is a uranyl nitrate hexahydrate solid and a thorium oxalate hexahydrate solid, the MOX fuel powder is (UxTh1-x) O2; when the mixed actinide salt is a uranyl nitrate hexahydrate solid and a plutonium oxalate hexahydrate solid, the MOX fuel powder is (UxPu1-x) O2. According to the method provided by the invention, the raw materials are simple, the preparation process flow of the MOX fuel powder composed of UO2 and PuO2 (or ThO2) can be greatly simplified, the use of process reagents is reduced, and no process waste liquid is generated, so that the MOX fuel powder preparation method which is simple, convenient, high in production efficiency, free of waste liquid and more economical and green is provided.

A system is described that includes a sputter target and a magnetic element array including multiple sets of magnets arranged to have a Hall-Effect region that extends along a length of the sputter target. The elongated sputtering electrode material tube is interposed between the magnetic array and an object to be deposited with a sputtered material from the sputter target. During a direct current high-power impulse magnetron sputtering operation, the system performs a depositing on a surface of the object by generating and controlling an ion and neutral particle flux by: providing a vacuum apparatus containing a sputter target holder electrode; first generating a high-power pulsed plasma magnetron discharge with a high-current negative direct current (DC) pulse to the sputter a target holder electrode; and second generating a configurable positive voltage kick pulse to the sputter target holder electrode after terminating the negative DC pulse.

System and procedure for the inspection of the surface of a nuclear fuel rod for the automatic detection, localization and characterization of defects, comprising a plurality of point cloud acquisition systems and translation means for the nuclear fuel rod; where the system also comprises processing means capable of transforming the point cloud into a height map, locally thresholding for the segmentation of the height map and obtaining the discontinuities in said map, classifying the discontinuities in different geometric shapes to obtain the area, length, width, position and orientation, projecting the defect on the y-axis to obtain its depth and calculating the equivalent function and its second derivative to obtain the points where the depth of the defect is maximum.

The invention discloses a radiation-resistant high-entropy alloy magnetron sputtering coating and a preparation method thereof, and belongs to the technical field of radiation-resistant coating materials. On the basis of the multi-element synergistic effect and lamination interface design of the high-entropy alloy, FeCrNi and FeNiCrMn are used as target materials, and the coating with the nanometer lamination structure is prepared by accurately regulating and controlling the target current, the gas flow, the deposition time and other process parameters of magnetron sputtering; meanwhile, accurate control over the single-layer film thickness and the interface density is achieved by adjusting the coupling relation between the sputtering power and the deposition rate, and it is ensured that all unit layers are flat and compact, and interface combination is complete. And a multi-heterogeneous interface is formed through the design of a laminated interface, so that a defect capture network is formed, the hardness of a single-layer coating is improved, the hardening rate after irradiation can be lower than that of a traditional single-layer coating, and the problems of crystallization and brittleness failure induced by irradiation are effectively relieved.

The invention provides a preparation method of a coated particle dispersion fuel, which comprises the following steps: mixing silicon carbide powder and a binder according to a preset mass ratio, banburying and granulating to obtain a silicon carbide matrix feed; printing a silicon carbide shell green body by using powder extrusion printing equipment and the silicon carbide matrix feed; degreasing the silicon carbide shell green body by using a degreasing solvent to obtain a silicon carbide shell brown blank; a cavity of the silicon carbide shell brown blank is filled with cladding fuel particles, and pores of the cladding fuel particles are filled with silicon carbide powder; and filling the filled silicon carbide shell brown blank into a chemical vapor infiltration device, generating silicon carbide by the introduced methyl trichlorosilane, filling a gap between the silicon carbide powder and the silicon carbide shell green blank with the silicon carbide, and obtaining the coated particle dispersion fuel after the chemical vapor infiltration is completed. By adopting powder extrusion printing and chemical vapor infiltration methods, the problems that the irradiation swelling resistance of existing coated particle dispersion fuel is reduced, the heat conductivity is low, and the loading capacity of coated fuel particles is limited are solved.

The invention provides a reactor core structure capable of controlling an assembly clearance and a manufacturing method thereof. The reactor core structure comprises a reactor core heat management element and a filling material; wherein the base body is provided with a plurality of assembly holes; the reactor core heat management element comprises a fuel rod or a heat pipe; the reactor core heat management element is assembled in the assembly hole of the base body; the filling material is filled in an assembly gap between the reactor core heat management element and the assembly hole; and the filling material is a shape memory alloy. The reactor core structure can improve the safety margin of the heat pipe reactor.

The invention belongs to the technical field of processing of nuclear reactor control rod neutron absorber materials, and particularly relates to a preparation method of a nuclear-grade hafnium cast ingot. The method comprises the following steps: preparing sponge hafnium into an electrode block; performing vacuum electron beam melting on the electrode block for at least two times to obtain a finished cast ingot; and processing the finished cast ingot to prepare the nuclear-grade hafnium cast ingot which can be used for processing the control rod profile for the nuclear reactor assembly. According to the preparation method of the nuclear-grade hafnium cast ingot, the tensile strength, the welding performance and the creep performance of a nuclear-grade hafnium profile can be effectively improved; meanwhile, the technological process is simplified, and the technological economy and the production efficiency are remarkably improved; in addition, sponge hafnium is directly adopted for vacuum electron beam melting, so that the cost of raw materials is greatly reduced. According to the method, the application performance of the nuclear-grade hafnium profile is improved, meanwhile, the process is simplified, the production efficiency is improved, the production cost is reduced, and the economical efficiency of nuclear-grade hafnium profile manufacturing is greatly improved.

The invention relates to industrial fuel rod feeding equipment, and belongs to the technical field of pipe machining and conveying equipment. The industrial fuel rod feeding equipment comprises a feeding device, a first feeding device, a conveying device, a second feeding device and a discharging device which are sequentially arranged in the first direction, industrial fuel rods are arranged on the feeding device side by side, and the axial direction of the industrial fuel rods is the second direction; the first feeding device comprises a plurality of first material taking pieces arranged in the second direction, the first material taking pieces ascend to jack up the industrial fuel rods placed on the feeding device, and the height of the ends, close to the feeding device, of the first material taking pieces is lower than that of the ends, close to the conveying device, of the first material taking pieces; the second feeding device comprises a plurality of second material taking pieces, the output end of the first driving piece is connected with the middles of the second material taking pieces, and the first driving piece drives the second material taking pieces to turn over so as to jack up the industrial fuel rods placed on the conveying device. According to the industrial fuel rod feeding equipment provided by the embodiment of the invention, the yield of produced industrial fuel rods can be improved.

The present invention belongs to the technical field of ceramic preparation, and relates to a preparation method and device for a high-purity porous boron carbide nuclear control rod. The present invention uses boron trichloride gas as the boron source, methane as the carbon source, argon as the carrier gas and protective gas, and hydrogen as the catalytic gas and reducing gas to prepare a high-purity porous boron carbide nuclear control rod. The method of increasing the deposition temperature of boron carbide step by step and region by region from the back to the front is adopted, which can not only improve the deposition rate of boron carbide, but also ensure that the physical and mechanical properties of each part of the prepared high-purity porous boron carbide nuclear control rod are consistent. By changing the particle size of the boron carbide powder for preparing the boron carbide blank and coordinating the adjustment of temperature, flow rate, pressure and deposition time, the porosity and pore size of the prepared high-purity porous boron carbide can be regulated and a high total boron and carbon content can be obtained, so as to meet various actual requirements.

Provided are a hollow radioactive containment fuel containing a burnable poison, a preparation method therefor and the use thereof. The hollow radioactive containment fuel containing a burnable poison comprises a hollow fuel area and a fuel-free protective layer covering the periphery of the fuel area; the hollow fuel area comprises a matrix, and a fuel element and a burnable poison which are distributed in the matrix, wherein the fuel element is an isotropic coated fuel particle, and the burnable poison is an isotropic coated burnable poison particle. The present invention can realize highly compact and safe radioactive containment of a reactor fuel, ensure that radioactive products, especially fission gas, are not released into the environment accidentally, stably provide a fission site for the core of a miniature nuclear power pile for a long period of time, effectively confine the radioactive fission products inside the fuel, and guarantee the safe and stable operation of a reactor.

Systems, structures, devices, and fabrication processes for ceramic matrix composites suitable for use in a nuclear reactor environment and other applications requiring materials that can withstand high temperatures and / or highly corrosive environments are disclosed. In one aspect, a ceramic composite structure is provided. The structure comprises a chamber including an external shell and a hollow space inside the external shell. The external shell includes an inner composite layer including a first composite structure, a middle composite layer placed outside of the inner composite layer, the middle composite layer including a second composite structure that is different from the first composite structure, and an outer monolithic layer that has a spatially uniform material property and placed outside of the middle composite layer.

A covering for reinforcing a base layer of a nuclear fuel cladding is provided. The covering comprises a first layer configured to cover a first portion of the outer surface of the base layer of the nuclear fuel cladding, a second layer surrounding the first layer and the base layer and a third layer surrounding the second layer. The first layer comprises a fiber based material, the second layer comprises an interfacing material and the third layer comprises Chromium. A reinforced cladding for nuclear fuel and a method for producing a reinforced nuclear fuel cladding are also provided.

The invention discloses a zirconium alloy fuel rod end plug composite welding method and a zirconium alloy fuel rod, and belongs to the field of welding. The zirconium alloy fuel rod end plug composite welding method comprises the following steps that a zirconium alloy end plug and a zirconium alloy fuel rod cladding are spliced together and fixed, and an inert gas environment is provided after vacuumizing; firstly, a zirconium alloy end plug and a zirconium alloy fuel rod cladding are subjected to TIG welding, and meanwhile ultrasonic stirring and electromagnetic stirring are provided; then, TIG welding is conducted on an inflation hole of the zirconium alloy end plug, and ultrasonic stirring and electromagnetic stirring are provided at the same time; and after welding is completed, a welding area is subjected to polishing and quality detection. According to the method, air holes in the zirconium alloy welding area can be effectively eliminated, uniform distribution of structures and components is promoted, and the welding quality and the corrosion resistance of the welding area are improved.

The invention discloses a cold rolling die with a straight rib thin-wall cladding pipe, a production process and the cladding pipe, and relates to the technical field of reactor fuel cladding, the cold rolling die comprises a cold rolling outer die for controlling the forming of the outer contour of a pipeline and a cold rolling core head for controlling the inner diameter; the cold rolling outer die is a die with a hollow area inside, the hollow area comprises a pitch circle section and a fixed rib section, and the fixed rib section is provided with at least one section of rib groove; a pipeline forming die cavity is formed by hollow areas of the two cold rolling outer dies, and a roll gap is formed between the two cold rolling outer dies; when the cold rolling die is used for producing the cladding pipe, the requirement for room-temperature plasticity of cladding materials in the forming process is low, the quality of the surface of the cladding pipe cannot be affected in the forming process, the quality of a formed product is high, and the cold rolling die is simple in structure, low in manufacturing cost and suitable for popularization and application. The thin-wall cladding tube with the straight ribs produced by the cold rolling die is good in surface quality, and the ribs of the cladding tube are good in mechanical property.

A system is described that includes a sputter target and a magnetic element array including multiple sets of magnets arranged to have a Hall-Effect region that extends along a length of the sputter target. The elongated sputtering electrode material tube is interposed between the magnetic array and an object to be deposited with a sputtered material from the sputter target. During a direct current high-power impulse magnetron sputtering operation, the system performs a depositing on a surface of the object by generating and controlling an ion and neutral particle flux by: providing a vacuum apparatus containing a sputter target holder electrode; first generating a high-power pulsed plasma magnetron discharge with a high-current negative direct current (DC) pulse to the sputter a target holder electrode; and second generating a configurable positive voltage kick pulse to the sputter target holder electrode after terminating the negative DC pulse.

The invention relates to a nuclear fuel cladding produced with a substrate (14) which is made of pure zirconium or of a zirconium based alloy and a multilayer protective coating (16) which covers a surface (14B) of the substrate (14), the protective coating (16) comprising a main layer (18) made of pure chromium and one or more additional layers (20), each additional layer (20) being made of pure chromium or from a material made of chromium and, additionally, oxygen and / or nitrogen, with the possible presence of unavoidable impurities.

The invention provides a high-strength winding thin-wall SiC composite cladding tube and a preparation method thereof. A preparation method of a high-strength winding thin-wall SiC composite cladding tube comprises the steps that silicon carbide fibers are wound and laid around a core mold, the winding pre-tightening force is smaller than or equal to 10 N. The winding mode comprises the first mode that one layer of annular winding is conducted firstly, then one layer of spiral winding is conducted, and the number of fiber intersection points in the whole annular direction at a certain position of the outer surface of the core mold is 1. One-layer annular winding is carried out firstly, then two-layer spiral winding is carried out, the number of fiber intersection points in the whole annular direction at a certain position of the outer surface of the core mold is 3, and a prefabricated body is obtained; carrying out a densification deposition process on the preform, wherein the densification deposition process comprises PyC pyrolytic carbon interface deposition, CVI chemical vapor infiltration and CVD chemical vapor deposition; and precise inner circle and outer circle machining is conducted, and the SiC composite cladding pipe is obtained. According to the preparation method disclosed by the invention, through a specific dry winding mode and a densification deposition process, the SiC composite material tube blank is higher in density and better in mechanical property.

The invention discloses a cladding tube for a lithium cold space nuclear reactor and a preparation method of the cladding tube, and belongs to the technical field of cladding tube structures, and the cladding tube is of an interlayer structure formed by sequentially overlapping a first W-Re alloy layer, a first WSi2 coating, a SiCf / SiC composite material layer, a second WSi2 coating and a second W-Re alloy layer from inside to outside. According to the invention, the air tightness and corrosion resistance of the cladding tube are obviously improved, and the cladding tube for the lithium cold space nuclear reactor has the properties of strong toughness, light weight, corrosion resistance, sealing property and the like.

The invention discloses a double-layer cladding nuclear fuel rod and a preparation method thereof.The preparation method comprises the steps that S1, a metal cladding with one closed end is loaded into a SiC composite cladding tube with one closed end, and the outer surface of the metal cladding is in close fit with the inner surface of the SiC composite cladding tube; s2, loading the nuclear fuel pellet and the first pressure spring into the metal cladding; s3, a metal end plug is connected to the open end of the metal cladding in a sealed mode, and a metal fuel rod is formed; s4, a second pressure spring and a heat insulation block are arranged in the SiC composite cladding tube to abut against the metal fuel rod; and S5, the SiC end plug is sealed at the open end of the SiC composite cladding tube in a matched mode. The double-layer cladding nuclear fuel rod disclosed by the invention has the characteristics of corrosion resistance and high air tightness, can effectively resist a hydrothermal corrosion environment under a normal operation working condition and an accident working condition, and meanwhile, effectively reduces the risk of releasing fission gas; the overall reliability of the fuel rod is high.

The invention discloses a uranium dioxide pellet and a preparation method thereof. The uranium dioxide pellet is prepared from the following raw materials in percentage by mass: 0.1-0.3 wt% of a pore forming agent, 0.1-0.3 wt% of a lubricant, 0.03-0.15 wt% of an additive A, 12-15 wt% of an additive B and the balance of uranium dioxide, the additive A comprises at least one metal oxide, metal elements in the metal oxide are IVB group, VB group, VIB group or VIIB group elements, and the additive B is triuranium octaoxide; the preparation method comprises the following steps: S1, mixing: mixing the pore-forming agent, the additive A, the additive B and uranium dioxide; s2, granulating: pressing for the first time, sieving with a screen, and then adding a lubricant for mixing; s3, forming, wherein secondary pressing is conducted; and S4, sintering: sintering the green body in a certain sintering atmosphere at a certain sintering temperature. According to the method, the situation that the average grain size of the uranium dioxide pellet is too large is avoided, the high-temperature plastic deformation capacity of the uranium dioxide pellet is improved, and the fuel failure risk caused by the PCI effect can be effectively reduced.

A deployment system for a molten salt reactor includes a reactor module, a cooling module, a coolant preparation module, a fuel shipping module, and a fuel preparation module. Each of the reactor module, the cooling module, the coolant preparation module, the fuel shipping module, and the fuel preparation module may be supplied to a deployment site. Using the coolant preparation module, a coolant salt held within the reactor module may be transferred to the cooling module. Using the fuel preparation module, a fuel salt held within the fuel shipping module may be transferred to the reactor module.

The invention relates to a moderator element for a nuclear reactor, the moderator element comprises a shell and a core block, the core block is a metal hydride moderator and is packaged in the shell, and the shell is a ceramic shell or a metal shell and is composed of a shell body and a cover body which are connected in a sealed mode. The invention also relates to a preparation method of the moderator element for the nuclear reactor. According to the moderator element for the nuclear reactor, the shell is prepared through the additive manufacturing forming technology, then the heat treatment technology is combined, densified packaging of the moderator is achieved, the problems that the moderator is prone to oxidation and corrosion in the using process are solved, and the requirement of the advanced nuclear reactor type for the moderator is met.

The invention belongs to the technical field of nuclear fuel element surface protection, and particularly relates to a multi-layer composite (Cr, Al) Nx / Cr protective coating for a nuclear reactor zirconium alloy cladding and a preparation method of the multi-layer composite (Cr, Al) Nx / Cr protective coating. The coating adopts a multi-layer structure design consisting of a buffer layer, a middle layer and an outermost layer in sequence from inside to outside, wherein the buffer layer is a Cr coating; the middle layer is a nitrogen-saturated (Cr, Al) Nx coating, x is larger than or equal to 1, the middle layer is of a columnar crystal structure, and the hardness of the middle layer is 5-10 GPa; the outermost layer is a non-stoichiometric ratio (Cr, Al) Nx coating, x is larger than or equal to 0.6 and smaller than or equal to 0.9, a nanocrystalline structure is shown, and the hardness is 12-25 GPa. Component regulation, hardness gradient and a microstructure are subjected to collaborative design, so that the coating has excellent wear resistance, high oxidation resistance and structural integrity at the same time under a harsh nuclear working condition, the safety margin of the zirconium alloy cladding under normal service and accident working conditions is greatly improved, and the service life of the zirconium alloy cladding under normal service and accident working conditions is greatly prolonged.

According to the anti-oxidation UN-based composite fuel pellet and the preparation method thereof, silicon carbide (SiC) serves as an anti-oxidation performance reinforcing phase of the UN fuel pellet, SiC is distributed in a dispersed mode or continuously distributed in a UN fuel matrix in a three-dimensional mode, and by means of the intragranular-grain boundary synergistic reinforcing effect of SiC, the anti-oxidation UN-based composite fuel pellet can be used for preparing the anti-oxidation UN-based composite fuel pellet, and the anti-oxidation UN-based composite fuel pellet can be used for improving the anti-oxidation performance of the UN fuel pellet. And the oxidation resistance of the UN fuel pellet is remarkably improved. Intragranular modification generated by solid solution reaction of trace SiC and UN can effectively enhance intrinsic oxidation resistance of a UN matrix, and meanwhile, excellent chemical inertness of a second phase of SiC can effectively inhibit grain boundary oxidation. By optimizing the morphology and distribution mode of the SiC second phase in the composite fuel pellet, the oxidation resistance of the composite fuel pellet can be further improved.

The invention belongs to the technical field of ceramic preparation, and relates to a preparation method and device of a high-purity porous boron carbide nuclear control rod. The high-purity porous boron carbide nuclear control rod is prepared by taking boron trichloride gas as a boron source, methane as a carbon source, argon as a carrier gas and a protective gas and hydrogen as a catalytic gas and a reducing gas, and the deposition temperature of boron carbide is increased by adopting a step-by-step and region-divided method from back to front, so that the deposition rate of boron carbide can be increased; the physical and mechanical properties of all parts of the prepared high-purity porous boron carbide nuclear control rod can be ensured to be consistent, the porosity and aperture of the prepared high-purity porous boron carbide can be regulated and controlled by changing the particle size of the boron carbide powder for preparing the boron carbide blank and cooperatively regulating the temperature, flow, pressure and deposition duration, and the high boron-carbon total content can be obtained; therefore, various actual requirements can be met.

Insulated fuel assembly core with plurality of fuel monoliths, exhaust support plate, exhaust shield assembly, and insulation layer in which the plurality of fuel monoliths are located axially along a longitudinal axis and each of the plurality of fuel monoliths has a shape of an eccentric cylinder and a composition including a fissionable fuel component. Channels in the exhaust support plate are oriented so that propellant gas flow through the exhaust support plate does not impinge the exhaust shield assembly. The insulated fuel assembly core is manufactured by forming a tensioned fuel monolith stack mandrel assembly using mandrels spacers and internal tensioning components and forming an insulation layer on an outer surface of the tensioned fuel monolith stack mandrel assembly by mandrel winding. The insulated fuel assembly core can be incorporated into a fuel assembly of nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

The invention discloses a nuclear power station zirconium alloy cladding tube surface oxide film standard sample preparation method, which comprises: S1, pre-treatment: carrying out physical grinding and chemical polishing on the zirconium alloy cladding tube surface, and carrying out vacuum thermal annealing treatment to obtain a zirconium alloy cladding tube sample; s2, plasma electrolytic oxidation: placing the preheated electrolyte in a stainless steel electrolytic bath, immersing the zirconium alloy cladding tube sample in the electrolyte, taking the zirconium alloy cladding tube sample as an anode, taking the stainless steel electrolytic bath as a cathode, and carrying out plasma electrolytic oxidation on the zirconium alloy cladding tube sample by adopting a bipolar pulse power supply, an oxidation film is generated on the surface of the zirconium alloy cladding tube sample, and a zirconium alloy cladding tube oxidation film sample is obtained; and S3, post-treatment: carrying out surface cleaning on the zirconium alloy cladding tube oxidation film sample. The preparation technology is simple, operation is easy and convenient, the growth speed of the oxidation film is high, the bonding strength of the oxidation film and the zirconium alloy matrix is high, and the film layer is compact and not prone to falling off.