KR20130117124A - Zirconium-ceramic hybrid tube for nuclear fuel rod cladding and method for manufacturing the same - Google Patents

Abstract

PURPOSE: A zirconium-ceramic hybrid tube for a nuclear fuel rod coating pipe and a manufacturing method thereof obtain the excellent ductility and low absorption properties of zirconium and the excellent heat resistance and corrosion resistance properties of ceramic by forming the zirconium-ceramic hybrid tube in a multi-layer structure of a zirconium tube and a ceramic tube. CONSTITUTION: A zirconium-ceramic hybrid tube (10) has a two-layer structure of a zirconium tube (11) and a fiber type ceramic tube (12). The ceramic tube is composed of fiber type ceramic or monolithic ceramic. The zirconium tube is composed of zirconium or a zirconium alloy. One or more ceramic tubes and one or more zirconium tubes form a multi-layer structure by being successively laminated in a concentric form. A graphite tube is interposed between the ceramic tube and the zirconium tube.

Description

Zirconium-ceramic hybrid tube for nuclear fuel rod cladding and method for manufacturing the same}

The present invention relates to a nuclear fuel rod cladding tube that traps nuclear fuel rods in a reactor of nuclear power plants and heavy water reactors, and prevents fission products from entering the cooling water. More particularly, the present invention relates to zirconium having excellent strength and ductility and excellent corrosion resistance and heat resistance. A zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube having complementary properties of ceramic materials, and a method of manufacturing the same.

In nuclear power plants, nuclear fuel rod cladding is exposed to cooling water at a pressure of about 15 MPa and a temperature of about 320 ° C. Nuclear fuel rod cladding tubes require mechanical reliability to suppress the release of fissile material therein and high thermal conductivity to efficiently transfer energy therein.

For this reason, zirconium alloys with excellent mechanical properties and low neutron absorption cross-sectional area are mainly used as nuclear fuel rod cladding tubes to withstand high temperature and high pressure corrosion environments and embrittlement due to neutron irradiation. That is, since zirconium alloys have high mechanical strength, creep resistance, corrosion resistance, thermal conductivity, and low neutron absorption at high temperatures, zirconium-based alloys (Zircaloy-4) developed in the early 1960s, including Zr-Nb-O-based M5 and Zr -Nb-Sn-Fe-based Zirlo alloys are widely used as nuclear fuel rod cladding tubes, and as disclosed in Korean Patent Publication No. 0296952 (registered on May 16, 2001), various technologies have been developed to improve corrosion resistance. come.

However, the zirconium fuel rod cladding can be relatively unreliable due to wear and corrosion in the nuclear fuel rod.In case of a nuclear power plant accident, the strength is weakened at a high temperature of 1,000 ℃ or higher, leading to a coolant accident. There are disadvantages that can lead to In addition, the metal-based fuel rod cladding tube has a problem in that its characteristics are deteriorated due to corrosion and hydrogen compound formation under reactor operating conditions.

In addition, recently, in order to increase the economic feasibility of nuclear power plants, high combustion, long cycle operation, high temperature coolant, and high pH operation have reached the limit that existing Zircaloy-4 fuel rod cladding cannot withstand, especially in the case of recent nuclear accidents. Due to the vulnerabilities of melting of zirconium alloys, various studies have been conducted to find materials for them.

Recently, a tube of ceramic material has been proposed as a nuclear fuel rod cladding tube, but ceramic composites have a limitation in that brittleness increases under neutron irradiation or it is difficult to withstand mechanical deformations imposed upon accidents. Low-ductility ceramics, especially at low temperatures, are more likely to be damaged by thermal shock and mechanical shock when charged at low temperatures, when fuel is replaced after prolonged combustion, and when temperatures drop in accident conditions.

The present invention is to solve the problems of the current fuel rod cladding tube of zirconium alloy, the object of the present invention is to have a zirconium having excellent toughness, ductility, creep resistance, thermal conductivity and low neutron absorption and heat resistance, corrosion resistance, low reactivity The present invention provides a zirconium-ceramic hybrid tube for nuclear fuel rod cladding and a method of manufacturing the same, by optimizing the properties of ceramics to maximize the advantages of both materials.

The zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube according to the present invention for achieving the above object comprises a ceramic tube made of a fibrous ceramic or monolithic ceramic and a zirconium tube made of zirconium or zirconium alloy, and at least one ceramic tube And one or more of the zirconium tubes are sequentially stacked in concentric circles to have a multilayer structure.

The zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube according to the present invention may further include a graphite tube interposed between the ceramic tube and the zirconium tube to increase the bonding force between the ceramic tube and the zirconium tube.

The ceramic tube may be made of a ceramic selected from a ceramic group consisting of SiC based, BN based, TiC based, TiN based, BeO based, ZrN based, ZrC based.

The ceramic tube preferably has a thermal conductivity of 0.01 to 0.5 cal · cm ⁻¹ s ⁻¹ · ° C. ⁻¹ .

The zirconium tube preferably contains at least 80% zirconium.

The method for producing a zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube according to the present invention for achieving the above object is a concentric circle of at least one ceramic tube made of fibrous ceramic or monolithic ceramic and at least one zirconium tube made of zirconium or zirconium alloy. It is characterized in that it is laminated in sequence to form a multilayer.

The method for manufacturing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to the present invention is selected from the lamination method, the insertion method, the graphite tube insertion method, the graphite coating method, the CVD coating method, and the bonding method by the ceramic tube and the zirconium tube. Can be combined by a joining method.

As described above, the zirconium-ceramic hybrid tube for the nuclear fuel rod cladding tube according to the present invention is composed of a multilayer structure of zirconium tube and ceramic tube, and has excellent toughness, ductility, creep resistance and low water absorption of ceramic and excellent corrosion resistance and heat resistance of ceramic. And corrosion resistance. Therefore, the mechanical reliability and safety is superior to that of a single zirconium tube or a single ceramic tube, and can be usefully used as a fuel cladding tube and a structure material within the reactor core of a light and heavy water reactor.

In addition, the zirconium-ceramic hybrid tube for the nuclear fuel rod cladding tube according to the present invention can contribute to improving the combustion of nuclear fuel and increasing the operating cycle of nuclear power, while maintaining the integrity of the nuclear fuel rod stably. Therefore, as a result, it is possible to improve the economics and safety of nuclear power plants, and reduce the risk of nuclear accidents and damages during nuclear accidents.

1 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a first embodiment of the present invention.
2 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a second embodiment of the present invention.
3 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a third embodiment of the present invention.
4 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a fourth embodiment of the present invention.
5 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a fifth embodiment of the present invention.
6 is a plan view showing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to a sixth embodiment of the present invention.

Hereinafter, with reference to the accompanying drawings, a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to the present invention and a manufacturing method thereof will be described in detail.

In describing the present invention, the sizes and shapes of the components shown in the drawings may be exaggerated or simplified for clarity and convenience of explanation. In addition, terms that are specifically defined in consideration of the configuration and operation of the present invention may vary depending on the intention or custom of the user or operator. These terms are to be construed in accordance with the meaning and concept consistent with the technical idea of the present invention based on the contents throughout the present specification.

The zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to the present invention has a multilayer structure in which one or more ceramic tubes and one or more zirconium tubes are sequentially stacked in a concentric manner. The ceramic tube is made of a fibrous ceramic or monolithic ceramic made of woven ceramic fibers, and the zirconium tube is made of zirconium (Zr) or zirconium alloy. Zirconium-ceramic hybrid tube for nuclear fuel rod cladding according to the present invention can take all of the high toughness and ductility of zirconium, low neutron absorption and high temperature corrosion resistance, heat resistance, creep resistance and high thermal conductivity of ceramics, Compared to the zirconium-ceramic hybrid tube, the mechanical reliability and safety are higher, and the characteristics as the fuel rod cladding tube are excellent.

The zirconium-ceramic hybrid tube for the fuel rod cladding tube according to the present invention includes an inner ceramic tube-an outer zirconium tube, an inner zirconium tube-an outer ceramic tube, an inner zirconium tube-an intermediate ceramic tube-an outer zirconium tube, an inner ceramic tube-an intermediate zirconium tube It can have various laminated structures, such as an external ceramic tube. In addition, a graphite tube may be interposed between the zirconium tube and the ceramic tube. Graphite tubes serve as an interlayer material to promote bonding between zirconium and ceramic tubes.

The thickness of the zirconium tube is preferably 5 to 500% of the thickness of the ceramic tube. If the thickness of the zirconium tube is less than 5% of the thickness of the ceramic tube, the ceramic becomes stronger and the risk of breakage due to brittleness under the neutron composition increases. In addition, when the thickness of the zirconium tube exceeds 500% of the thickness of the ceramic tube, sufficient heat resistance and corrosion resistance to the nuclear fuel rod cladding tube cannot be secured, and thus the replacement cycle is shortened and the life is shortened when used at high temperature.

Ceramic materials constituting the ceramic tube include SiC-Cg, SiC-hi-nic, SiC-Type-s, SiC-Tyranno, SiC-based, BN-based, TiC-based, TiN-based, BeO-based, ZrN-based, and ZrC-based. Various ceramic materials may be used. The ceramic tube preferably has a thermal conductivity of 0.01 to 0.5 cal · cm ⁻¹ s ⁻¹ · ° C. ⁻¹ . If the thermal conductivity of the ceramic tube is less than 0.01cal · cm ⁻¹ s ⁻¹ · ° C. ⁻¹ , the heat transfer efficiency is lowered, and thus, energy cannot be effectively transferred, which may lead to a decrease in power generation efficiency. And thermal conductivity of the ceramic tube is ^{0.5cal · cm -1 s -1 · ℃} - may result in problems ¹ goes stress on the fuel rod by the thermal expansion difference the larger the thermal energy delivered exceeds a.

Zirconium tubes can be made of commercially pure zirconium with a purity of 99.99% or zirconium alloys containing at least 80% zirconium. If the zirconium content is less than 80%, it may not have excellent mechanical reliability and low neutron absorption, and may cause a problem that the efficiency of energy transfer is greatly reduced. Zircaloy-4, Zr-Nb-O (M5), Zr-1Nb-1Sn-0.1Fe and the like may be used as the zirconium alloy.

The specific structure of the zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube according to the present invention is as shown in Figs. Hereinafter, various embodiments of a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube according to the present invention will be described with reference to FIGS. 1 to 6.

1 and 2, the zirconium-ceramic hybrid tube 10, 20 for the nuclear fuel rod cladding tube according to the first and second embodiments of the present invention is a zirconium tube 11 and a fibrous ceramic tube 12 ) Has a two-layer structure. The zirconium-ceramic hybrid tube 10 for the nuclear fuel rod cladding tube according to the first embodiment of the present invention has a structure in which the fibrous ceramic tube 12 is concentrically stacked on the outer side of the zirconium tube 11, and the second The zirconium-ceramic hybrid tube 20 for the nuclear fuel rod cladding tube according to the embodiment has a structure in which zirconium tubes 11 are stacked in a concentric manner on the outer side of the fibrous ceramic tube 12. The zirconium tube 11 and the fibrous ceramic tube 12 are firmly bonded to each other through various bonding methods.

The zirconium-ceramic hybrid tube 30 for the nuclear fuel rod cladding tube according to the third embodiment of the present invention shown in FIG. 3 has a three-layer structure of a zirconium tube 11-a fibrous ceramic tube 12-a zirconium tube 11 To have. The inner and outer surfaces of the fibrous ceramic tube 12 are tightly adhered to the inner zirconium tube 11 and the outer zirconium tube 11 without any gaps.

In the zirconium-ceramic hybrid tube 40 for the nuclear fuel rod cladding tube according to the fourth embodiment of the present invention shown in FIG. 4, two ceramic tubes 13 and 12 are sequentially stacked on the outer side of the zirconium tube 11. It has a layer structure. The middle of the two ceramic tubes 13, 12 is the monolithic ceramic tube 13, and the outermost is the fibrous ceramic tube 12.

The zirconium-ceramic hybrid tube 50 for the nuclear fuel rod cladding tube according to the fifth embodiment of the present invention shown in FIG. 5 has a three-layer structure of a zirconium tube 11-graphite tube 14-fibrous ceramic tube 12 To have. The graphite tube 14 is interposed between the zirconium tube 11 and the fibrous ceramic tube 12 to increase their bonding force, and the zirconium tube 11 and the fibrous ceramic tube 12 through various bonding methods. And tightly combined without gaps.

A zirconium-ceramic hybrid tube 60 for a nuclear fuel rod cladding tube according to a sixth embodiment of the present invention shown in FIG. 6 is a zirconium tube 11-graphite tube 14-monolithic ceramic tube 13-fibrous ceramic The tube 12 has a four-layer structure. The zirconium-ceramic hybrid tube 60 for the nuclear fuel rod cladding tube has an excellent bonding force between the zirconium tube 11 and the monolithic ceramic tube 13 through the graphite tube 14, and the two ceramic tubes 12. Since (13) is provided, it is excellent in the high temperature corrosion resistance, flame resistance, creep resistance, and thermal conductivity which are the characteristics of a ceramic material.

As described above, the zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube according to the present invention is composed of a multilayer structure of zirconium tube and ceramic tube, and has excellent toughness and ductility and low water absorption of zirconium and excellent corrosion resistance, heat resistance and corrosion resistance of ceramic. Take it all. Therefore, the mechanical reliability and safety is superior to that of a single zirconium tube or a single ceramic tube, and can be usefully used as a fuel cladding tube and a structure material within the reactor core of a light and heavy water reactor.

In addition, the zirconium-ceramic hybrid tube for the nuclear fuel rod cladding tube according to the present invention can contribute to improving the combustion of nuclear fuel and increasing the operating cycle of nuclear power while maintaining the integrity of the nuclear fuel rod when used as a structural material. Therefore, it is possible to improve the economics and safety of nuclear power plants, and to reduce the risk of nuclear accidents and damages during nuclear accidents.

The zirconium tube and ceramic tube constituting the zirconium-ceramic hybrid tube for the nuclear fuel rod cladding tube according to the present invention can be bonded to each other through various bonding methods. The combination of zirconium tube and ceramic tube is characterized by physical attraction due to adhesion, chemical solid-phase reactions involving the formation of new phases, sintering by various mass transfer such as surface diffusion, volume diffusion, particle growth, crystallization from liquid phase, It can be made by dissolution by a liquid phase and interdiffusion at the bonding interface. Specific bonding methods include the following lamination method, insertion method, graphite tube insertion method, graphite coating method, CVD coating method, and bonding method using an adhesive. In addition, various methods such as microwave bonding and brazing bonding may be used to join the zirconium tube and the ceramic tube.

In the lamination method, a method of laminating a ceramic tube sequentially on a zirconium tube and then joining it through a high pressure process, or coating a ceramic fiber woven in a grid form on a zirconium tube and joining it through a high pressure process and processing. And densely wound ceramic fibers along the axis on a zirconium tube and then joining them through a high pressure process and processing.

Insertion method is a method of joining the zirconium tube or ceramic tube by high pressure insertion on the ceramic tube or zirconium tube, it is a bonding method that can close the gap between each tube as close as possible.

Graphite tube insertion method is a bonding method for inserting a graphite tube on a ceramic tube or zirconium tube to fix the high pressure, then inserting and fixing a ceramic tube or zirconium tube in the graphite tube.

Graphite coating is a method of homogeneously applying graphite powder on the surface of a ceramic tube or zirconium tube, and then inserting it at high pressure to buffer the gaps between the tubes with graphite to bond them.

The CVD coating method is a method of depositing ceramic or zirconium on a ceramic tube or zirconium tube using heat and plasma by placing a ceramic tube or zirconium tube in a reaction chamber and supplying gas.

Bonding method using an adhesive is a method of uniformly applying an adhesive using a phenol, polyamide, silicone, epoxy, etc. on a ceramic tube or zirconium tube, and then fixing the ceramic tube or zirconium tube.

Hereinafter, the present invention will be described in more detail based on Examples and Test Examples.

The following examples are merely illustrative of the present invention, the present invention is not limited to the examples. The zirconium-ceramic hybrid tube according to the following examples and the tube according to the comparative example were manufactured to have a length of 366 cm, an outer diameter of 11.5 mm, and an inner diameter of 10.16 mm.

Example  One: SiC  With ceramic materials Zr -One Nb -One Sn -0.1 Fe  Alloy By lamination  Zirconium-Ceramic Hybrid Tube

A zirconium-ceramic hybrid tube was manufactured by bonding a SiC (silicon carbide) ceramic tube and a Zr-1Nb-1Sn-0.1Fe zirconium alloy tube by lamination. The manufacturing process of such a zirconium-ceramic hybrid tube is as follows.

a) securing the SiC ceramic tube to the tube holder

b) charging a liquid molten Zr-1Nb-1Sn-0.1Fe alloy in a fixed SiC ceramic tube

c) bonding and cooling the liquid molten Zr-1Nb-1Sn-0.1Fe alloy with the SiC tube by rotating the tube holder at high speed;

Here, the SiC ceramic tube and the Zr-1Nb-1Sn-0.1Fe zirconium alloy tube have the same thickness with a thickness ratio of 5: 5.

In order to confirm the performance of the zirconium-ceramic hybrid tube according to Example 1, the tensile strength of each SiC ceramic tube, Zr-1Nb-1Sn-0.1Fe zirconium alloy tube and the zirconium-ceramic hybrid tube according to Example 1 The ductility and fracture toughness were measured and these were compared with the measurement results. Tensile strength and ductility of each tube were measured using Universal Materials Testing Machine (UNITED, US / SSTM) at room temperature and high temperature (600 ℃), and fracture toughness using Nano Indentation System (MTS USA) at room temperature. The measurement results are shown in Table 1 below.

As a result of tensile strength measurement, SiC tube showed about 590 MPa, Zr-1Nb-1Sn-0.1Fe zirconium alloy tube showed about 850 MPa, and the zirconium-ceramic hybrid tube according to Example 1 of the present invention showed a tensile strength value of about 660 MPa. Analysis of the measurement results, it was found that the zirconium-ceramic hybrid tube according to the present invention is superior in tensile strength than the ceramic material. In particular, it can be seen that the tensile strength at high temperature of the zirconium-ceramic hybrid tube according to Example 1 of the present invention is greater than that of the zirconium alloy tube, which is excellent in heat resistance. As a result, it can be seen that the zirconium-ceramic hybrid tube according to the present invention takes advantage of both the ceramic material and the zirconium material.

Fracture toughness measurements showed that the fracture toughness of the SiC tube was about 2.5 Mpa / m ² and the fracture toughness of the Zr-1Nb-1Sn-0.1Fe zirconium alloy tube was about 65 Mpa / m ² . In addition, the fracture toughness of the zirconium-ceramic hybrid tube according to Example 1 was measured to be about 51.7 Mpa / m ² , indicating that the zirconium-ceramic hybrid tube according to the present invention can greatly improve low fracture toughness, which is a problem of ceramic materials. I could confirm it.

Example  2 : SiC  After applying graphite to the ceramic tube, Zr -One Nb -One Sn Zirconium-Ceramic Hybrid Tubing Fabricated by Bonding -0.1Fe Tubes

 A zirconium-ceramic hybrid tube was prepared by applying graphite to the SiC ceramic tube outer surface and then joining the processed Zr-1Nb-1Sn-0.1Fe tube. The manufacturing process of the SiC-graphite-Zr-1Nb-1Sn-0.1Fe zirconium-ceramic hybrid tube is as follows.

a) securing the SiC ceramic tube to the holder

b) applying graphite to the outer surface of the fixed SiC ceramic tube

c) improving Zr-1Nb-1Sn-0.1Fe tube to improve mechanical properties

d) bonding the processed Zr-1Nb-1Sn-0.1Fe tube onto the graphite coated SiC tube

Tensile strength measurement results at room temperature and high temperature (600 ℃) of the SiC-Graphite-Zr-1Nb-1Sn-0.1Fe zirconium-ceramic hybrid tube according to Example 2 (Universal Materials Testing Machine (UNITED, US / SSTM) equipment ) And fracture toughness measurement results (using Nano Indentation System (MTS USA)) are shown in Table 1 below. Examining the tensile strength and fracture toughness of the zirconium-ceramic hybrid tube according to Example 2, the zirconium-ceramic hybrid tube according to Example 2 has a higher fracture toughness than the ceramic material, and the tensile strength at high temperature is a zirconium alloy The tensile strength of the tube is greater than that of the ceramic material and the zirconium material.

Example  3: processed Zr -One Nb -One Sn -0.1 Fe  Woven into the tube SiC  Ceramic covering Zirconium-Ceramic Hybrid Tube

 A zirconium-ceramic hybrid tube was prepared by coating a SiC ceramic having a fiber structure on the outer surface of the processed Zr-1Nb-1Sn-0.1Fe tube. The preparation process of Zr-1Nb-1Sn-0.1Fe-SiC (fiber) zirconium-ceramic hybrid tube according to Example 3 is as follows.

a) improving the mechanical properties by processing Zr-1Nb-1Sn-0.1Fe tube

b) securing the Zr-1Nb-1Sn-0.1Fe tube to the holder

c) coating the fiber structure SiC on the outer surface of the fixed Zr-1Nb-1Sn-0.1Fe tube

Tensile strength measurement results at room temperature and high temperature (600 ℃) of Zr-1Nb-1Sn-0.1Fe-SiC (fiber) zirconium-ceramic hybrid tube according to Example 3 (Universal Materials Testing Machine (UNITED, US / SSTM) equipment ) And fracture toughness measurement results (using Nano Indentation System (MTS USA)) are shown in Table 1 below. Examining the tensile strength and fracture toughness of the zirconium-ceramic hybrid tube according to Example 3, the zirconium-ceramic hybrid tube according to Example 3 had a higher fracture toughness and a higher tensile strength at high temperature than the ceramic material. The tensile strength of the tube is greater than that of the ceramic material and the zirconium material.

Example  4: processed Zr -One Nb -One Sn -0.1 Fe  Apply graphite to the tube and weave with fiber SiC To Coated  Zirconium-Ceramic Hybrid Tube

 Zr-1Nb-1Sn-0.1Fe-graphite-SiC (fiber) zirconium hybrid hybrid tube was prepared by coating graphite on the outer surface of the processed Zr-1Nb-1Sn-0.1Fe tube and then coating the SiC ceramic having a fiber structure. . The manufacturing process of Zr-1Nb-1Sn-0.1Fe-graphite-SiC (fiber) zirconium-ceramic hybrid tube according to Example 4 is as follows.

a) improving the mechanical properties by processing Zr-1Nb-1Sn-0.1Fe tube

b) securing the Zr-1Nb-1Sn-0.1Fe tube to the holder

c) applying graphite to the outer surface of the fixed Zr-1Nb-1Sn-0.1Fe tube

d) coating the fiber structure SiC on the graphite coated Zr-1Nb-1Sn-0.1Fe tube

Tensile strength measurement results at room temperature and high temperature (600 ° C.) of Zr-1Nb-1Sn-0.1Fe-Graphite-SiC (fiber) zirconium-ceramic hybrid tube according to Example 4 (Universal Materials Testing Machine (UNITED, US / SSTM) ) And the fracture toughness measurement results (using Nano Indentation System (MTS USA)) are shown in Table 1 below. The tensile strength and fracture toughness measurement results of the zirconium-ceramic hybrid tube according to Example 4 were examined. The tensile strength of the tube is greater than that of the ceramic material and the zirconium material.

The embodiments of the present invention described above and shown in the drawings should not be construed as limiting the technical idea of the present invention. The scope of protection of the present invention is limited only by the matters described in the claims, and those skilled in the art can improve and modify the technical idea of the present invention in various forms. Accordingly, these modifications and variations are intended to fall within the scope of the present invention as long as it is obvious to those skilled in the art.

10 to 60: Zirconium-Ceramic Hybrid Tube for Nuclear Fuel Rod Cladding
11: zirconium tube 12: fibrous ceramic tube
13: monolithic ceramic tube 14: graphite tube

Claims (10)

Ceramic tubes made of fibrous ceramics or monolithic ceramics; And
A zirconium tube made of zirconium or zirconium alloy,
A zirconium-ceramic hybrid tube for nuclear fuel rod cladding, wherein at least one ceramic tube and at least one zirconium tube are sequentially stacked in a concentric manner.
The method of claim 1,
A zirconium-ceramic hybrid tube for nuclear fuel rod cladding, further comprising a graphite tube interposed between the ceramic tube and the zirconium tube to increase the bonding force between the ceramic tube and the zirconium tube.
The method of claim 1,
The ceramic tube is a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube, characterized in that the ceramic selected from the ceramic group consisting of SiC-based, BN-based, TiC-based, TiN-based, BeO-based, ZrN-based, ZrC-based.
The method of claim 1,
The ceramic tube is a zirconium-ceramic hybrid tube for nuclear fuel rod cladding tube, characterized in that it has a thermal conductivity of 0.01 ~ 0.5 cal · cm ⁻¹ s ⁻¹ · ° C. ⁻¹ .
The method of claim 1,
The zirconium tube is a zirconium-ceramic hybrid tube for nuclear fuel rod cladding, characterized in that containing at least 80% zirconium.
Fabrication of a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube by stacking one or more ceramic tubes made of fibrous or monolithic ceramics and one or more zirconium tubes made of zirconium or zirconium alloy in a concentric manner in order to form a multilayer Way.
The method according to claim 6,
A zirconium-ceramic hybrid for nuclear fuel rod cladding tube, wherein the ceramic tube and the zirconium tube are joined by a bonding method selected from a lamination method, an insertion method, a graphite tube insertion method, a graphite coating method, a CVD coating method, and an adhesive bonding method. Method of manufacturing the tube.
The method according to claim 6,
The ceramic tube is a method for producing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube, characterized in that the ceramic selected from the ceramic group consisting of SiC-based, BN-based, TiC-based, TiN-based, BeO-based, ZrN-based, ZrC-based.
The method according to claim 6,
Said ceramic tube has a thermal conductivity of 0.01 to 0.5 cal · cm ⁻¹ s ⁻¹ · ° C. ⁻¹ , and a method for producing a zirconium-ceramic hybrid tube for a nuclear fuel rod cladding tube.
The method according to claim 6,
The zirconium tube is a method for producing a zirconium-ceramic hybrid tube for nuclear fuel rod cladding, characterized in that containing at least 80% zirconium.

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