CN113035384A - Coated cladding for nuclear fuel rods and method of manufacture - Google Patents
Coated cladding for nuclear fuel rods and method of manufacture Download PDFInfo
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- CN113035384A CN113035384A CN202110281859.4A CN202110281859A CN113035384A CN 113035384 A CN113035384 A CN 113035384A CN 202110281859 A CN202110281859 A CN 202110281859A CN 113035384 A CN113035384 A CN 113035384A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to a coating cladding for a nuclear fuel rod and a manufacturing method, the coating cladding comprises: a cladding tube body; the coating is arranged on the outer side wall of the cladding tube body; the protective layer, the protective layer includes a plurality of archs that set up along the cladding pipe body is radial, and a plurality of archs all set up the outside at the coating. According to the scheme provided by the application, the protrusion is arranged on the outer side of the coating on the cladding tube body, and can prevent other parts from directly contacting with the surface coating in the processes of rod pulling, transferring operation and the like, so that the surface coating is prevented from being scratched or scraped.
Description
Technical Field
The invention relates to the technical field of nuclear fuel, in particular to a coating cladding for a nuclear fuel rod and a manufacturing method thereof.
Background
In the current commercial light water reactor, the nuclear fuel assembly used consists of an array of nuclear fuel rods, typically in the form of a 17X17 array, including 264 fuel rods, 24 guide tubes and 1 instrumentation tube. The fuel rod is formed by sealing and welding a zirconium alloy cladding tube, and ceramic oxide fuel pellets are filled in the fuel rod.
The service environment of the nuclear fuel assembly is high temperature and high pressure water, and for a Pressurized Water Reactor (PWR), the temperature can reach 360 ℃, and the pressure can reach 15.5 MPa. Under normal operating conditions, the zirconium alloy cladding that makes up the nuclear fuel rod undergoes oxidation in contact with the coolant, which forms brittle oxides that affect the mechanical properties of the cladding. Meanwhile, in the nuclear fuel assembly, there is a risk that the zirconium alloy cladding will be worn out due to the influence of foreign matter or flow-induced vibration. For this reason, the nuclear industry has attempted to increase the wear resistance of the cladding by applying a surface coating to the surface of the zirconium alloy cladding. In fact, the nuclear industry has successfully controlled the corrosion of zirconium alloy cladding at very low levels under normal operating conditions by continuing improvements in zirconium alloy cladding design, operational control, and improvements in water chemistry.
However, under accident conditions, the reactor core temperature typically exceeds 700 ℃, and may even reach as high as 1200 ℃, at which time the coolant will be in the form of high temperature steam. Under the hypothetical accident conditions of Reactivity Introduction Accident (RIA), loss of coolant accident (LOCA), water loss of a spent fuel pool and the like, the zirconium alloy cladding can be exposed to the high-temperature water vapor environment, and the rapid reaction of the zirconium alloy and the high-temperature water vapor can generate a large amount of hydrogen, so that the risk of hydrogen explosion exists. During subsequent quenching, the zirconium alloy cladding may fail at a large scale due to embrittlement. Thus, it is desirable to limit as much as possible the high temperature oxidation of the zirconium alloy cladding. For this reason, Accident Tolerant Fuel (Accident Tolerant Fuel) is being developed in the nuclear industry, and a recent important direction is to apply a high temperature corrosion resistant coating on the surface of zirconium alloy.
As noted above, the nuclear industry has attempted to improve the application of coatings to zirconium alloy surfaces in order to resist corrosion under normal operating conditions, erosion, and high temperature oxidative corrosion under hypothetical accident conditions.
For the cladding tube with the zirconium alloy surface coated with the coating, the problem that the surface coating on the zirconium alloy cladding tube is scratched or scraped off is easily caused in the process of rod pulling operation and the like of a fuel rod processed and manufactured by a nuclear fuel assembly, so that the overall performance of the fuel rod is influenced.
Disclosure of Invention
In view of the above, it is desirable to provide a coated cladding for a nuclear fuel rod and a manufacturing method thereof, which solve the problem that the surface coating on the zirconium alloy cladding tube is easily scratched or scraped off during the rod pulling operation of the conventional fuel rod.
The present invention provides a coated cladding for a nuclear fuel rod, comprising:
a cladding tube body;
a coating disposed on an outer sidewall of the cladding tube body;
a protective layer comprising a plurality of projections disposed radially along the cladding tube body, the plurality of projections each being disposed outside the coating.
According to the coating cladding for the nuclear fuel rod, the bulges are arranged on the outer side of the coating on the cladding tube body, and can prevent other parts from directly contacting with the surface coating in the processes of rod pulling, transferring operation and the like, so that the surface coating is prevented from being scratched or scraped off.
In one embodiment, the coating comprises a pure chromium coating, and the plurality of protrusions form a net structure.
In one embodiment, the hollow part of the reticular structure is provided with coating grains.
In one embodiment, the mesh structure is formed of any one of a triangular structure, a circular structure, an elliptical structure, or other polygonal structure, or,
the mesh structure is formed of at least two of a triangular structure, a circular structure, an elliptical structure, or other polygonal structure.
In one embodiment, the plurality of protrusions continuously form any one of a vertical line structure, a diagonal line structure or a thread structure on the coating surface.
In one embodiment, the protrusions continuously form at least two of a vertical line structure, a diagonal line structure or a thread structure on the coating surface.
In one embodiment, coating grains are arranged between the grains on the vertical grain structure, the diagonal grain structure or the thread structure.
The present invention also provides a method of manufacturing a coated cladding for a nuclear fuel rod, for use in a coated cladding for a nuclear fuel rod as described in any one of the embodiments of the present application, the method comprising:
coating a layer of pure chromium coating on the surface of the cladding tube;
and processing protrusions on the surface of the pure chromium coating to form a protective layer.
In one embodiment, the step of processing the protrusions on the surface of the pure chromium coating comprises: processing the bulges on the surface of the pure chromium coating by adopting a mask mode or a chemical plating mode.
In one embodiment, the step of processing the protrusions on the surface of the pure chromium coating comprises: depositing another chromium coating on the surface of the pure chromium coating by adopting a chemical deposition method;
a laser etching process is used to etch away a portion of the chrome coating on the other chrome coating to form the protrusion.
Drawings
FIG. 1 is a schematic structural view of a coated cladding for a nuclear fuel rod provided in accordance with an embodiment of the present invention;
FIG. 2 is yet another schematic view of FIG. 1;
FIG. 3 is another schematic structural view of a coated cladding for a nuclear fuel rod provided in accordance with an embodiment of the present invention;
FIG. 4 is a schematic view of yet another construction of a coated cladding for a nuclear fuel rod according to an embodiment of the present invention.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in detail below. In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. This invention may, however, be embodied in many different forms and should not be construed as limited to the embodiments set forth herein.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced device or element must have a particular orientation, be constructed and operated in a particular orientation, and are not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or intervening elements may also be present. When an element is referred to as being "connected" to another element, it can be directly connected to the other element or intervening elements may also be present. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and the like as used herein are for illustrative purposes only and do not denote a unique embodiment.
In one embodiment of the present invention, as shown in fig. 1, there is provided a coated cladding for a nuclear fuel rod, including: the cladding tube comprises a cladding tube body 10, a coating and a protective layer, wherein the coating is arranged on the outer side wall of the cladding tube body 10, the protective layer comprises a plurality of protrusions arranged along the radial direction of the cladding tube body 10, and the protrusions are all arranged on the outer side of the coating.
By adopting the technical scheme, the bulge is arranged on the outer side of the coating on the cladding tube body, and can prevent other parts from directly contacting with the surface coating in the processes of rod pulling, transferring operation and the like, so that the surface coating is prevented from being scratched or scraped off.
In some embodiments, the coating in the present application includes a pure chromium coating, a mesh structure 20 (as shown in fig. 1) is defined by a plurality of protrusions, the present invention employs a magnetron sputtering process to coat a pure chromium coating with a thickness of 15 μm on the surface of the cladding tube body 10, and further employs a masking method to coat a mesh structure 20, i.e. a pure chromium coating, with a thickness of 3 μm on the basis of the surface coating. In the technological processes of rod pulling and the like for assembling the fuel assembly, the contact abrasion of the grillwork only influences the reticular structure 20, so that the scratch of the surface coating of the bottom layer is avoided;
meanwhile, the net structure 20 of the present invention also increases the heat exchange between the cooling fluid and the cladding tube, enhances the heat transfer capacity of the fuel rod, and improves the thermal safety margin of the fuel rod. Meanwhile, the mesh structure can moderately improve the bending resistance of the fuel rod on the premise of not changing the area of the flow channel.
The processing of the mesh structure can adopt one or more of the processes of screen printing, Physical Vapor Deposition (PVD), plasma spraying, arc ion plating, thermal spraying, cold spraying, chemical deposition, etching (etching) and the like, and the cladding tube body can also be other alloy cladding or metal composite tube cladding.
It should be noted that the structure of the pure chromium coating is used as the network structure in the embodiment of the present application, and in other alternative schemes, other structures may be adopted, for example, carbides such as SiC, ZrC, etc., and both carbide coatings have been successfully applied to the high temperature gas cooled reactor and exhibit good radiation stability. Research shows that SiC is hardly oxidized and can replace zirconium alloy claddingOne of the materials of (1). The preparation method of the zirconium alloy surface carbide coating mainly comprises plasma chemical vapor deposition, radio frequency sputtering coating, ion beam mixed deposition and the like, the preparation temperature of the processes is lower, and if the preparation temperature of the coating by the radio frequency sputtering coating method does not exceed 400 ℃, the stability of the zirconium alloy matrix structure is favorably maintained. Meanwhile, the SiC coating has a good protection effect in a low-temperature corrosive water environment, and the hydrogen absorption amount of the matrix can be obviously reduced; the oxidation weight gain of the coating cladding at high temperature water vapor environments such as 750 and 1200 ℃ is 1/5 of the zirconium alloy matrix, and the coating cladding shows good oxidation resistance; or nitrides such as TiN, TiAlN, ZrN and the like have higher hardness, melting point and high thermal conductivity and excellent corrosion resistance, and the nitride coating on the surface of the zirconium alloy is mainly used for reducing the damage of the inching wear in the reactor to the cladding tube. The preparation method of the zirconium alloy surface nitride coating mainly comprises cathodic arc physical vapor deposition, pulsed laser deposition, cold spraying technology and the like. Results of conventional corrosion (360 ℃, 18.7MPa) and supercritical water corrosion tests (500 ℃, 25MPa) show that the TiN and TiAlN coating can obviously reduce the corrosion rate of the cladding; alternatively, metal coatings such as FeCrAl and Cr, etc., rely on oxidation products such as Cr for their oxidation resistance2O3Or Al2O3A dense protective film is formed that hinders the diffusion of oxygen to the matrix, thereby reducing the oxidation rate of the cladding tube. The preparation method of the zirconium alloy surface metal coating mainly comprises arc ion plating, laser coating, magnetron sputtering and the like, and the obtained coating material has excellent performance. The specific material of the net-like structure is not particularly limited as long as the above-mentioned structural material can achieve the object of the present application.
In some embodiments, as shown in fig. 2, the hollow portion of the mesh structure 20 in the present application is provided with coating pattern points 201. The provision of coating spots 201 may further reduce the likelihood of the external component contacting the surface coating.
It should be noted that the structural shape of the coating pattern points in the embodiments of the present application is only an example, and in other alternative solutions, other structural shapes may also be adopted, for example, polygons or other irregular patterns. The structural shape of the coating pattern points is not particularly limited as long as the structural shape can achieve the object of the present application.
In some embodiments, the mesh structure 20 of the present application includes any one of a triangular structure, a circular structure, an elliptical structure, or other polygonal structure.
Further, the mesh structure 20 of the present application may also include at least two of a triangular structure, a circular structure, an oval structure, or other polygonal structures.
The net structures with the structural shapes are all pure chromium coatings with the thickness of 3 mu m coated on the surface of the cladding tube body by adopting a magnetron sputtering process, and then a layer of net structure is coated on the basis of the surface coatings by adopting a mask mode.
It should be noted that the structure of the pure chromium coating is used as the network structure in the embodiment of the present application, and in other alternative schemes, other structures may be adopted, for example, carbides such as SiC, ZrC, etc., and both carbide coatings have been successfully applied to the high temperature gas cooled reactor and exhibit good radiation stability. Studies have shown that SiC undergoes little oxidation and is one of the possible materials to replace zirconium alloy cladding. The preparation method of the zirconium alloy surface carbide coating mainly comprises plasma chemical vapor deposition, radio frequency sputtering coating, ion beam mixed deposition and the like, the preparation temperature of the processes is lower, and if the preparation temperature of the coating by the radio frequency sputtering coating method does not exceed 400 ℃, the stability of the zirconium alloy matrix structure is favorably maintained. Meanwhile, the SiC coating has a good protection effect in a low-temperature corrosive water environment, and the hydrogen absorption amount of the matrix can be obviously reduced; the oxidation weight gain of the coating cladding at high temperature water vapor environments such as 750 and 1200 ℃ is 1/5 of the zirconium alloy matrix, and the coating cladding shows good oxidation resistance; or nitrides such as TiN, TiAlN, ZrN and the like have higher hardness, melting point and high thermal conductivity and excellent corrosion resistance, and the nitride coating on the surface of the zirconium alloy is mainly used for reducing the damage of the inching wear in the reactor to the cladding tube. The preparation method of the zirconium alloy surface nitride coating mainly comprises cathodic arc physical vapor deposition, pulsed laser deposition, cold spraying technology and the like. Conventional etching (360 ℃, 18.7MPa) and supercritical water corrosion test (500 ℃, 25MPa) show that the TiN and TiAlN coating can obviously reduce the corrosion rate of the cladding; alternatively, metal coatings such as FeCrAl and Cr, etc., rely on oxidation products such as Cr for their oxidation resistance2O3Or Al2O3A dense protective film is formed that hinders the diffusion of oxygen to the matrix, thereby reducing the oxidation rate of the cladding tube. The preparation method of the zirconium alloy surface metal coating mainly comprises arc ion plating, laser coating, magnetron sputtering and the like, and the obtained coating material has excellent performance. The specific material of the net-like structure is not particularly limited as long as the above-mentioned structural material can achieve the object of the present application.
As shown in figure 3, the cold spraying process is adopted to coat a 20-micron chromium coating on the surface of the cladding tube body, the 20-micron chromium coating is the coating, and on the basis, a chemical deposition method is adopted to deposit a 5-micron chromium coating, the 5-micron chromium coating is the protective layer, so that a chromium coating with the thickness of 25 microns is formed. On the basis of the surface coating with the thickness of 25 mu m, a laser etching method is adopted to etch the chromium coating with the thickness of 5 mu m to form a bulge, and in the technological processes of a pull rod and the like for assembling the fuel assembly, the bulge is worn by contacting with the lattice frame, so that scratches on the surface coating of the bottom layer are avoided.
It should be noted that the structure of the pure chromium coating is used as the protective layer in the embodiment of the present application, and in other alternative, other structures may be adopted, for example, carbides such as SiC, ZrC, etc., and both carbide coatings have been successfully applied to a high temperature gas cooled reactor and exhibit good radiation stability. Studies have shown that SiC undergoes little oxidation and is one of the possible materials to replace zirconium alloy cladding. The preparation method of the zirconium alloy surface carbide coating mainly comprises plasma chemical vapor deposition, radio frequency sputtering coating, ion beam mixed deposition and the like, the preparation temperature of the processes is lower, and if the preparation temperature of the coating by the radio frequency sputtering coating method does not exceed 400 ℃, the stability of the zirconium alloy matrix structure is favorably maintained. Meanwhile, the SiC coating has a good protection effect in a low-temperature corrosive water environment, and the hydrogen absorption amount of the matrix can be obviously reduced; in a high temperature water vapor environment such as 750 and 1The oxidation weight increase of the coating cladding at 200 ℃ is 1/5 of that of the zirconium alloy matrix, and the coating cladding shows good oxidation resistance; or nitrides such as TiN, TiAlN, ZrN and the like have higher hardness, melting point and high thermal conductivity and excellent corrosion resistance, and the nitride coating on the surface of the zirconium alloy is mainly used for reducing the damage of the inching wear in the reactor to the cladding tube. The preparation method of the zirconium alloy surface nitride coating mainly comprises cathodic arc physical vapor deposition, pulsed laser deposition, cold spraying technology and the like. Results of conventional corrosion (360 ℃, 18.7MPa) and supercritical water corrosion tests (500 ℃, 25MPa) show that the TiN and TiAlN coating can obviously reduce the corrosion rate of the cladding; alternatively, metal coatings such as FeCrAl and Cr, etc., rely on oxidation products such as Cr for their oxidation resistance2O3Or Al2O3A dense protective film is formed that hinders the diffusion of oxygen to the matrix, thereby reducing the oxidation rate of the cladding tube. The preparation method of the zirconium alloy surface metal coating mainly comprises arc ion plating, laser coating, magnetron sputtering and the like, and the obtained coating material has excellent performance. The specific material of the protective layer is not particularly limited as long as the structural material described above can achieve the object of the present application.
In some embodiments, as shown in fig. 3, the plurality of protrusions of the present application continuously form any one of a standing grain structure 301, a diagonal structure 302, or a thread structure 303 on the coating surface.
Further, the plurality of protrusions in the present application continuously form at least two of the rib structure 301, the diagonal structure 302, or the thread structure 303 on the coating surface.
It should be noted that the structural shape of the protrusions in the embodiments of the present application is only an example, and in other alternatives, other structural shapes, such as a trapezoid or a sawtooth structure, may also be adopted. The specific structural shape of the protrusions is not particularly limited in the present application as long as the above-described structure can achieve the object of the present application.
In some embodiments, the stripes on the vertical stripe structure, the diagonal stripe structure or the thread structure are provided with coating stripe points, and the arrangement of the coating stripe points can further reduce the possibility that the external part contacts the surface coating.
In some embodiments, as shown in fig. 4, the protective layer 401 in the present application is composed of a network structure formed by protrusions and a strip-shaped structural layer formed by protrusions.
Specifically, a chromium coating of 15 μm was applied to the surface of the cladding pipe body 10 using a plasma spray process. And preparing a reticular coating with the thickness of 4 mu m according to the reticular structure of the figure 4 by adopting an electroless plating mode on the basis of the surface coating. In the technological process of a pull rod and the like for assembling the fuel assembly, the net-shaped structure coating is contacted and worn with the grid, so that the scratch of the surface coating of the bottom layer is avoided.
It should be noted that the structural shape of the protective layer in the embodiment of the present application is only an example, and in other alternative schemes, other structural shapes may be adopted, for example, a trapezoidal or zigzag structure. The specific structural shape of the protective layer is not particularly limited as long as the above-described structure can achieve the object of the present application.
The present invention also provides a method of manufacturing a coated cladding for a nuclear fuel rod, for use in a coated cladding for a nuclear fuel rod as described in any one of the embodiments of the present application, the method comprising:
coating a layer of pure chromium coating on the surface of the cladding tube;
and processing protrusions on the surface of the pure chromium coating to form a protective layer.
In some embodiments, the step of machining the protrusions on the surface of the pure chromium coating in the present application comprises: processing the bulges on the surface of the pure chromium coating by adopting a mask mode or a chemical plating mode. For example, firstly, a magnetron sputtering process is adopted to coat a pure chromium coating with the thickness of 15 μm on the surface of the zirconium alloy cladding tube, and then a layer of protrusion with the thickness of 3 μm is coated in a masking mode on the basis of the surface coating. In the technical processes of rod pulling and the like for assembling the fuel assembly, the contact abrasion of the grillwork only influences the bulge, and the scratch of the surface coating of the bottom layer is avoided.
In some embodiments, the step of machining the protrusions on the surface of the pure chromium coating in the present application comprises: depositing another chromium coating on the surface of the pure chromium coating by adopting a chemical deposition method; a laser etching process is used to etch away a portion of the chrome coating on the other chrome coating to form the protrusion.
For example, a cold spray process is adopted to coat a 20 μm chromium coating on the surface of the cladding tube body, the 20 μm chromium coating is the coating, and then a chemical deposition method is adopted to deposit another 5 μm chromium coating to form a chromium coating with the thickness of 25 μm in total. On the basis of the surface coating with the thickness of 25 mu m, a laser etching method is adopted to etch the chromium coating with the thickness of 5 mu m to form a bulge, and in the technological processes of a pull rod and the like for assembling the fuel assembly, the bulge is worn by contacting with the lattice frame, so that scratches on the surface coating of the bottom layer are avoided.
The technical features of the embodiments described above may be arbitrarily combined, and for the sake of brevity, all possible combinations of the technical features in the embodiments described above are not described, but should be considered as being within the scope of the present specification as long as there is no contradiction between the combinations of the technical features.
The above-mentioned embodiments only express several embodiments of the present invention, and the description thereof is more specific and detailed, but not construed as limiting the scope of the invention. It should be noted that, for a person skilled in the art, several variations and modifications can be made without departing from the inventive concept, which falls within the scope of the present invention. Therefore, the protection scope of the present patent shall be subject to the appended claims.
Claims (10)
1. A coated cladding for a nuclear fuel rod, comprising:
a cladding tube body (10);
a coating provided on an outer sidewall of the cladding tube body (10);
a protective layer comprising a plurality of protrusions arranged radially along the cladding tube body (10), the plurality of protrusions each being arranged outside the coating.
2. The nuclear fuel rod coating cladding shell according to claim 1, wherein the coating comprises a pure chromium coating, and a plurality of the protrusions enclose a mesh structure (20).
3. The nuclear fuel rod coating cladding according to claim 2, characterized in that the hollow portion of the network (20) is provided with coating striation points (201).
4. The nuclear fuel rod coating cladding according to claim 2, characterized in that the mesh structure (20) is formed of any one of a triangular structure, a circular structure, an oval structure or other polygonal structure, or,
the net structure (20) is formed of at least two of a triangular structure, a circular structure, an elliptical structure, or other polygonal structure.
5. The nuclear fuel rod coating cladding as recited in claim 1 wherein the plurality of protrusions continuously form any one of a standing grain structure, a diagonal structure, or a thread structure on the coating surface.
6. The nuclear fuel rod coating cladding as recited in claim 1 wherein the plurality of protrusions continuously form at least two of a standing grain structure, a twill structure, or a thread structure on the coating surface.
7. The nuclear fuel rod coating cladding as recited in claim 5 or 6 wherein the striations on the ribbing, twill or thread structure are provided with coating striation points therebetween.
8. A method of manufacturing a coated cladding for a nuclear fuel rod, the coated cladding for a nuclear fuel rod as claimed in any one of claims 1 to 7, the method comprising:
coating a layer of pure chromium coating on the surface of the cladding tube;
and processing protrusions on the surface of the pure chromium coating to form a protective layer.
9. The method of making a coated cladding for a nuclear fuel rod of claim 8 wherein the step of machining the protrusions on the surface of the pure chrome coating includes:
processing the bulges on the surface of the pure chromium coating by adopting a mask mode or a chemical plating mode.
10. The method of making a coated cladding for a nuclear fuel rod of claim 8 wherein the step of machining the protrusions on the surface of the pure chrome coating includes:
depositing another chromium coating on the surface of the pure chromium coating by adopting a chemical deposition method;
a laser etching process is used to etch away a portion of the chrome coating on the other chrome coating to form the protrusion.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US20230368931A1 (en) * | 2022-05-10 | 2023-11-16 | Westinghouse Electric Company Llc | Fuel cladding covered by a mesh |
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| WO2023220149A3 (en) * | 2022-05-10 | 2024-02-15 | Westinghouse Electric Company Llc | Fuel cladding covered by a mesh |
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