Iron-based cladding tritium-blocking material for fusion reactor, and preparation method and application of iron-based cladding tritium-blocking material

Abstract

The invention discloses an iron-based cladding tritium-resistant material for a fusion reactor as well as a preparation method and application of the iron-based cladding tritium-resistant material, and a tritium-resistant layer of the iron-based cladding tritium-resistant material sequentially comprises a matrix / SiO2 / Cr2O3 from inside to outside to form a composite tritium-resistant layer; based on 100% of the tritium blocking layer, the tritium blocking layer comprises, by mass, 11.8% < = Cr < = 12.2%, 2.46% < = Si < = 2.53%, 2.8% < = W < = 3.1%, 2.7% < = Al < = 3.1%, 0.05% < = Y < = 0.06%, Be < = 0.5% and the balance iron and inevitable impurities. The FeCrWSiAl-based cladding tritium-resistant material added with Be is finally prepared through the processes of burdening, high-frequency induction smelting and founding, casting molding, hot rolling, warm rolling or cold rolling, annealing, in-situ oxidation and the like. The strength, high temperature resistance and corrosion resistance of the alloy are effectively improved through alloying, the tritium resistance layer with certain tritium resistance is prepared through the in-situ oxidation technology, and tritium self-sustaining of the fusion reactor cladding structure material is facilitated.

Description

Technical Field

[0001] The present invention relates to an iron-based alloy material, in particular to a Be-added FeCrWSiAl-based cladding tritium-barrier material, which is applied to the technical field of fusion reactor cladding structural materials. Background Art

[0002] The continuous development of thermonuclear fusion has placed higher demands on various technical indicators of fusion reactors. The tritium barrier performance of the blanket material directly affects the tritium self-sustaining and safety of the fusion reactor during operation. The tritium barrier layers formed by in-situ oxidation that have been studied so far have a PRF value of no more than 100, far below the 200 required for the ITER project. Among them, the tritium barrier layer composed of SiO2 and Cr2O3 has a higher PRF value and has good compatibility and tritium barrier capability in the Pb-Li environment of 300-600°C. Currently, tritium barrier layers are mostly prepared by coating or surface infiltration of elements such as Al followed by in-situ oxidation. The former will reduce the effectiveness of the tritium barrier layer in the Pb-Li environment, thereby reducing the tritium barrier capability. The latter will form intermediate compounds in the alloy, making the formation of the tritium barrier layer difficult. Currently, the requirements for cladding structural materials are becoming increasingly higher. Not only are they required to have excellent tritium-barrier performance, but they are also required to have excellent mechanical properties and corrosion resistance under working conditions. There is an urgent need to develop cladding structural materials that are integrated with tritium-barrier, corrosion-resistant and high-temperature resistant. Summary of the Invention

[0003] In order to solve the problems existing in existing materials and technologies, the purpose of the present invention is to overcome the shortcomings of existing materials and technologies, and to provide an iron-based cladding tritium-barrier material for fusion reactors, its preparation method and its application. The iron-based cladding tritium-barrier material of the present invention is a cladding structural material with integrated tritium resistance, corrosion resistance and high temperature resistance. The present invention prepares a cladding structural material with integrated tritium resistance, corrosion resistance and high temperature resistance. The cladding structural material with integrated tritium resistance, corrosion resistance and high temperature resistance of the present invention has the characteristics of high temperature resistance, excellent mechanical properties and a thick tritium barrier layer. It can not only ensure a certain tritium barrier performance, but also ensure better mechanical properties under working conditions. The production process is simple and easy to process. The present invention can be used as a tritium self-sustaining cladding structural material for fusion reactors.

[0004] In order to achieve the above-mentioned purpose, the present invention adopts the following inventive concept:

[0005] SiO2 has a certain tritium barrier capability. Due to different preparation processes, its PRF value ranges from 10 to 100. It has high corrosion resistance, thermal stability, and adhesion. At the same time, Si can serve as an alloying element to strengthen the matrix and improve the strength of the alloy, so that the alloy can maintain a certain strength while having a certain tritium barrier performance. Cr2O3 also has a certain tritium barrier capability. As a composite tritium barrier layer, it can be combined with SiO2 to make the PRF value exceed 100. It has excellent thermal stability and corrosion resistance. Cr can serve as an alloying element to strengthen the matrix and improve the mechanical properties of the alloy. The addition of Al can inhibit the precipitation of the harmful σ phase in the alloy. Be has a low thermal neutron absorption cross-section of about 0.009ba, which has a good solid solution strengthening effect in the alloy, and can improve the weldability and weld corrosion resistance of the alloy, and improve the recovery ability of the tritium barrier layer. The iron-based cladding tritium barrier material for fusion reactors in the present invention has the advantages of high PRF value, corrosion resistance, excellent thermal stability, and good adhesion to the matrix.

[0006] According to the above invention concept, the present invention adopts the following technical solutions:

[0007] A tritium-barrier iron-based cladding material for a fusion reactor comprises a tritium-barrier layer composed of a matrix, SiO2, and Cr2O3 from the inside out, forming a composite tritium-barrier layer. Taking the tritium-barrier layer as 100%, the tritium-barrier layer comprises the following components in percentage by mass: 11.8%≤Cr≤12.2%, 2.46%≤Si≤2.53%, 2.8%≤W≤3.1%, 2.7%≤Al≤3.1%, 0.05%≤Y≤0.06%, Be≤0.5%, and the remaining components are iron and unavoidable impurities.

[0008] Preferably, the Be content in the tritium barrier layer is: 0.1%≤Be≤0.5%.

[0009] Preferably, the tritium barrier layer of the alloy material has a thickness of 0.11 to 0.872 μm.

[0010] More preferably, the tritium barrier layer of the alloy material has a thickness of 0.38 to 0.87 μm.

[0011] A method for preparing the iron-based cladding tritium barrier material for a fusion reactor according to the present invention comprises the following steps:

[0012] a. Using a high-frequency vacuum induction melting process, when the raw materials are batched, the main raw material components are prepared according to the following mass percentage (wt.%) composition: Cr: 11.8~12.2%, Si: 2.46~2.53%, W: 2.8~3.1%, Al: 2.7~3.1%, Y: 0.05~0.06%, Be≤0.5%, and the remaining raw material components are iron and unavoidable impurities. After batching, all the raw materials weighed are subjected to high-frequency vacuum induction melting to obtain an alloy melt, which is then cast to obtain an alloy ingot;

[0013] b. The alloy ingot prepared in step a is sequentially subjected to hot rolling, warm rolling or cold rolling, annealing and in-situ oxidation processes to finally obtain an iron-based cladding tritium barrier material for a fusion reactor.

[0014] Preferably, in step a, a high-frequency vacuum induction melting process is used to place the prepared raw materials into a high-frequency vacuum induction furnace and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat it to 1600℃±20℃, and keep it warm for at least 1 minute to obtain an alloy melt, which is then cast into shape.

[0015] Preferably, in step b, the alloy ingot obtained by casting the alloy melt prepared in step a is subjected to hot rolling, wherein the hot rolling temperature is controlled to be not less than 1100° C. and the rolling is repeated at least 3 times; and then warm rolling is performed, wherein the warm rolling temperature is controlled to be not less than 600° C. and the rolling is repeated at least 3 times;

[0016] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0017] Finally, an in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C ± 10°C, and the oxidation atmosphere is a still air atmosphere or a mixed atmosphere of argon and water vapor. Finally, a finished product of an iron-based cladding tritium barrier material for a fusion reactor is obtained.

[0018] Preferably, in step b, when the oxidizing atmosphere is a mixed atmosphere of water vapor, the water vapor is heated in a water bath at 65° C., and is driven by argon gas into the tube furnace to form a mixed atmosphere of water vapor.

[0019] An application of the iron-based cladding tritium barrier material for a fusion reactor of the present invention can be used as a high-temperature resistant and tritium-barrier material in a Pb-Li environment of 300-600°C, and can also be used as a structural material.

[0020] Preferably, the iron-based cladding tritium barrier material for a fusion reactor is used as a tritium permeation barrier material in any one of the cladding structures of a fusion reactor reaction.

[0021] The present invention effectively improves the strength, high temperature resistance and corrosion resistance of the alloy through alloying, and prepares a tritium barrier layer with certain tritium barrier performance through an in-situ oxidation process, which is beneficial to the tritium self-sustaining of the fusion reactor blanket structural material.

[0022] Fe has high strength and toughness. After alloying and heat treatment, the alloy structure can be improved to have better high-temperature mechanical properties.

[0023] The atomic number of Cr is 24, its relative atomic mass is 52, and the density of metallic chromium is about 7.15 g / cm 3 As an alloying element in iron, it can improve the strength and corrosion resistance of the alloy and form a Cr2O3 tritium barrier layer. The preferred amount of Cr used in the present invention (wt.%) is 11.8-12.2.

[0024] The atomic number of Si is 14, its relative atomic mass is 28, and the density of metallic silicon is about 2.34 g / cm 3 As an alloying element in iron, Si can improve the strength and corrosion resistance of the alloy and form a SiO2 tritium barrier layer. The preferred amount of Si in the present invention (wt.%) is 2.46 to 2.53.

[0025] The atomic number of W is 74, its relative atomic mass is 183, and the density of metallic tungsten is about 19.35 g / cm 3 As an alloying element in iron, W can improve the strength of the alloy and form Fe2W type Laves phase to further strengthen the matrix and refine the grains. The preferred amount of W in the present invention (wt.%) is 2.8 to 3.1.

[0026] The atomic number of Y is 39, its relative atomic mass is 89, and the density of metallic yttrium is about 4.47 g / cm 3 , can be used as a trace element in iron to improve the bonding strength between the tritium barrier layer and the substrate, and can also improve the strength of the alloy and inhibit high-temperature brittleness. The preferred amount of Y in the present invention (wt.%) is 0.05-0.06.

[0027] The atomic number of Be is 4, its relative atomic mass is 9, and the density of metallic yttrium is about 1.85 g / cm 3 , which can play the role of fine grain strengthening and solid solution strengthening in iron, improve the recovery ability of the tritium barrier layer, and improve the weldability and weld corrosion resistance of the alloy. The preferred amount of Be (wt.%) in the present invention is ≤0.5.

[0028] The Be-added FeCrWSiAl-based cladding tritium-barrier material of the present invention is used as a cladding structural material for the outer layer of a fusion reactor to ensure tritium self-sustaining during the nuclear fusion process and prevent tritium leakage.

[0029] Compared with the prior art, the present invention has the following obvious outstanding substantial features and significant advantages:

[0030] 1. Compared with the tritium barrier coatings currently under study, the tritium barrier layer prepared by in-situ oxidation of the FeCrWSiAl-based cladding tritium barrier material with Be added in the present invention is more tightly bonded to the substrate and has better heat resistance;

[0031] 2. Compared with the in-situ oxidation tritium barrier layer currently studied, the tritium barrier layer prepared by in-situ oxidation of the FeCrWSiAl-based cladding tritium barrier material with Be added in the present invention is a double-layer tritium barrier layer. The tritium barrier capabilities of the two tritium barrier layers are combined to effectively reduce the tritium penetration effect;

[0032] 3. The invention's Be-added FeCrWSiAl-based cladding tritium barrier material contains Cr, Si, W, Al, Y, or Be, all of which enhance the alloy's strength. Cr, Y, and Be also improve the adhesion, continuity, and self-healing properties of the tritium barrier layer. Cr and Si form a SiO2 / Cr2O3 tritium barrier layer, making it a promising candidate for future tritium barrier blankets. Al inhibits σ phase precipitation, and Be interacts with H and He to prevent their leakage, further ensuring the safety of fusion reactors.

[0033] 4. The FeCrWSiAl-based cladding tritium-barrier material with Be added in the present invention has good high-temperature performance and a simple production process; the iron-based cladding tritium-barrier material with Si-Cr-W-Al added in the present invention can be used as a cladding structural material that integrates tritium resistance, corrosion resistance, and high-temperature resistance. BRIEF DESCRIPTION OF THE DRAWINGS

[0034] Figure 1 This is a metallographic microstructure photograph of the iron-based cladding tritium barrier material according to Example 2 of the present invention.

[0035] Figure 2 This is a cross-sectional microstructure diagram of the tritium barrier layer of the iron-based cladding tritium barrier material according to Example 2 of the present invention. DETAILED DESCRIPTION

[0036] The above solution is further described below with reference to specific implementation examples. The preferred embodiments of the present invention are described in detail as follows:

[0037] Example 1:

[0038] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material without adding Be is provided, and the steps are as follows:

[0039] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0040]

[0041] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1600 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0042] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then warm rolling is performed, the warm rolling temperature is controlled to be 600°C and the rolling is repeated three times;

[0043] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0044] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C and the oxidation atmosphere is a mixed atmosphere of argon and water vapor. The water vapor is heated in a 65°C water bath and driven by argon into the tubular furnace, finally producing iron-based cladding tritium barrier material plates for fusion reactors.

[0045] Experimental testing demonstrates that the alloy material prepared in this embodiment has a tritium barrier layer thickness of 0.11 μm, ensuring excellent tritium permeation resistance in a Pb-Li environment at 300-600°C, making it a promising candidate for future fusion reactor blanket structural materials. The composite tritium barrier layer in this embodiment achieves a PRF value of 102 in a Pb-Li environment at 300-600°C. The Be content in this composite tritium barrier layer is zero. Therefore, while the Be-free FeCrWSiAl-based blanket tritium barrier material exhibits some tritium permeation resistance, it can still be used as an iron-based blanket tritium barrier material for fusion reactors.

[0046] Example 2:

[0047] This embodiment is basically the same as the first embodiment, with the following special features:

[0048] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material with Be added thereto includes the following steps:

[0049] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0050]

[0051] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1600 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0052] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then warm rolling is performed, the warm rolling temperature is controlled to be 600°C and the rolling is repeated three times;

[0053] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0054] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C and the oxidation atmosphere is a mixture of argon and water vapor. The water vapor is heated in a 65°C water bath and driven by argon into the tubular furnace, finally producing iron-based cladding tritium barrier material plates for fusion reactors.

[0055] Experimental tests have shown that the tritium barrier layer thickness of the alloy material prepared in this embodiment is 0.38 μm, which can ensure that the alloy has excellent tritium penetration resistance in a Pb-Li environment of 300-600°C, and is a better candidate material for the cladding structure material for future fusion reactors. Figure 1 This is a metallographic microstructure photograph of the iron-based cladding tritium barrier material of this embodiment. Figure 2 The cross-sectional microstructure diagram of the tritium barrier layer of the iron-based cladding tritium barrier material of this embodiment is shown in FIG. Figure 2 As can be seen, the tritium barrier layer of this embodiment has a composite layer structure of matrix / SiO2 / Cr2O3. The interface layers between the different layers form interlayer transitions and diffusions, forming a strong connection between the different layers, with good connection strength, high bonding strength between the different layers, and resisting interlayer detachment. The composite tritium barrier layer of this embodiment achieves a PRF value of 118 in a Pb-Li environment at 300-600°C. Clearly, the PRF value of the FeCrWSiAl-based cladding tritium barrier material with Be added in this embodiment is significantly improved compared to Example 1. This embodiment effectively improves the alloy's strength, high temperature resistance, and corrosion resistance through alloying. Furthermore, a tritium barrier layer with certain tritium barrier properties is prepared through an in-situ oxidation process, which is beneficial for tritium self-sustaining in fusion reactor blanket structural materials.

[0056] Example 3:

[0057] This embodiment is basically the same as the above embodiment, with the following special features:

[0058] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material with Be added thereto includes the following steps:

[0059] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0060]

[0061] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1600 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0062] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then warm rolling is performed, the warm rolling temperature is controlled to be 600°C and the rolling is repeated three times;

[0063] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0064] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C and the oxidation atmosphere is a mixture of argon and water vapor. The water vapor is heated in a 65°C water bath and driven by argon into the tubular furnace, finally producing iron-based cladding tritium barrier material plates for fusion reactors.

[0065] Experimental testing demonstrated that the tritium barrier layer thickness of the alloy material prepared in this embodiment is 0.64 μm, ensuring excellent tritium permeation resistance in a Pb-Li environment at 300-600°C, making it a promising candidate for future fusion reactor blanket structural materials. The composite tritium barrier layer of this embodiment achieved a PRF value of 132 in a Pb-Li environment at 300-600°C. Clearly, the PRF value of the FeCrWSiAl-based cladding tritium barrier material with Be added in this embodiment is significantly improved compared to that of Example 1. This embodiment effectively improves the alloy's strength, high-temperature resistance, and corrosion resistance through alloying, and produces a tritium barrier layer with certain tritium resistance through an in-situ oxidation process, which is beneficial for tritium self-sustaining in fusion reactor blanket structural materials.

[0066] Example 4:

[0067] This embodiment is basically the same as the first embodiment, with the following special features:

[0068] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material with Be added thereto includes the following steps:

[0069] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0070]

[0071] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1600 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0072] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then warm rolling is performed, the warm rolling temperature is controlled to be 600°C and the rolling is repeated three times;

[0073] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0074] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C and the oxidation atmosphere is a mixture of argon and water vapor. The water vapor is heated in a 65°C water bath and driven by argon into the tubular furnace, finally producing iron-based cladding tritium barrier material plates for fusion reactors.

[0075] Experimental testing demonstrates that the alloy material prepared in this embodiment has a tritium barrier layer thickness of 0.87 μm, ensuring excellent tritium permeation resistance in a Pb-Li environment at 300-600°C, making it a promising candidate for blanket materials for future fusion reactors. The composite tritium barrier layer in this embodiment achieves a PRF value of 126 in a Pb-Li environment at 300-600°C. This significantly improves the PRF value of the FeCrWSiAl-based blanket tritium barrier material with Be added in this embodiment compared to the first embodiment. As the Be content in the composite tritium barrier layer increases, the tritium barrier performance of the composite tritium barrier layer decreases after the Be content exceeds 0.5 wt.%. Therefore, the present invention preferably uses a Be content of no more than 0.5 wt.%. This embodiment effectively improves the alloy's strength, high-temperature resistance, and corrosion resistance through alloying. Furthermore, the in-situ oxidation process produces a tritium barrier layer with sufficient tritium resistance, which is beneficial for tritium self-sustaining in fusion reactor blanket materials.

[0076] Embodiment 5:

[0077] This embodiment is basically the same as the above embodiment, with the following special features:

[0078] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material with Be added thereto includes the following steps:

[0079] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0080]

[0081]

[0082] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1580 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0083] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then cold rolled at room temperature and rolled three times;

[0084] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0085] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 840°C and the oxidation atmosphere is still air, and finally the iron-based cladding tritium barrier material plate for fusion reactor is produced.

[0086] Experimental testing demonstrates that the tritium barrier layer of the alloy material prepared in this embodiment has a thickness of approximately 0.15 μm, ensuring excellent tritium permeation resistance in a Pb-Li environment at 300-600°C, making it a promising candidate for future fusion reactor blanket materials. The composite tritium barrier layer of this embodiment achieved a PRF value of 108 in a Pb-Li environment at 300-600°C. This significantly improves the PRF value of the FeCrWSiAl-based cladding tritium barrier material with Be added in this embodiment compared to the first embodiment. This embodiment effectively enhances the alloy's strength, high-temperature resistance, and corrosion resistance through alloying. Furthermore, the in-situ oxidation process produces a tritium barrier layer with sufficient tritium resistance, which is beneficial for tritium self-sustaining in fusion reactor blanket materials.

[0087] Example 6:

[0088] This embodiment is basically the same as the above embodiment, with the following special features:

[0089] In this embodiment, a method for preparing a FeCrWSiAl-based cladding tritium barrier material with Be added thereto includes the following steps:

[0090] a. Using high-frequency vacuum induction melting process, when the raw materials are prepared, the raw materials are prepared according to the following mass percentage (wt.%):

[0091]

[0092] Mix the weighed raw materials after batching, put the prepared raw materials into a high-frequency vacuum induction furnace, and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat up to 1620 ° C, and keep the temperature for 1 minute, perform induction melting, obtain alloy melt, and cast into shape;

[0093] b. The alloy ingot obtained by casting the alloy melt prepared in step a is hot rolled, wherein the hot rolling temperature is controlled to be 1100°C and the rolling is repeated three times; and then cold rolled at room temperature and rolled three times;

[0094] Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature;

[0095] Finally, in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 860°C and the oxidation atmosphere is still air, and finally the iron-based cladding tritium barrier material plate for fusion reactor is produced.

[0096] Experimental testing indicates that the tritium barrier layer of the alloy material prepared in this embodiment has a thickness of approximately 0.66 μm, ensuring excellent tritium permeation resistance in a Pb-Li environment at 300-600°C, making it a promising candidate for future fusion reactor blanket materials. The composite tritium barrier layer of this embodiment achieved a PRF value of 135 in a Pb-Li environment at 300-600°C. This significantly improves the PRF value of the FeCrWSiAl-based cladding tritium barrier material with Be added in this embodiment compared to the first embodiment. This embodiment effectively improves the alloy's strength, high-temperature resistance, and corrosion resistance through alloying, and produces a tritium barrier layer with sufficient tritium resistance through an in-situ oxidation process, which is beneficial for tritium self-sustaining in fusion reactor blanket materials.

[0097] As can be seen from Examples 1 to 6 above, the FeCrWSiAl-based cladding tritium-barrier material, the iron-based alloy material of the above-mentioned embodiment of the present invention, has the following composition percentages by weight: 11.8% ≤ Cr ≤ 12.2%, 2.46% ≤ Si ≤ 2.53%, 2.8% ≤ W ≤ 3.1%, 2.7% ≤ Al ≤ 3.1%, 0.05% ≤ Y ≤ 0.06%, and Be ≤ 0.5%, with the remainder being iron and unavoidable impurities. After batching and high-frequency induction melting, the above-mentioned embodiment of the present invention is cast and then hot-rolled, warm-rolled, or cold-rolled, annealed, and subjected to in-situ oxidation processes to ultimately produce the Be-added FeCrWSiAl-based cladding tritium-barrier material sheet. The above-mentioned iron-based cladding tritium-barrier material for fusion reactors can be used as a high-temperature-resistant and tritium-barrier material, as well as a structural material. The iron-based cladding tritium barrier material for a fusion reactor can be used as a tritium permeation barrier material in any blanket structure of a fusion reactor reaction. The above-described embodiment of the present invention effectively improves the strength, high-temperature resistance, and corrosion resistance of the alloy through alloying, and produces a tritium barrier layer with certain tritium barrier properties through an in-situ oxidation process, which is beneficial to the tritium self-sustaining of the fusion reactor blanket structure material.

[0098] The above describes the embodiments of the present invention in conjunction with the accompanying drawings, but the present invention is not limited to the above embodiments. Various changes can be made according to the inventive purpose of the present invention. Any changes, modifications, substitutions, combinations or simplifications made according to the spirit and principles of the technical solution of the present invention should be equivalent replacement methods. As long as they comply with the inventive purpose of the present invention and do not deviate from the technical principles and inventive concepts of the present invention, they belong to the scope of protection of the present invention.

Claims

1. An iron-based cladding tritium barrier material for a fusion reactor, characterized by: The tritium barrier layer is composed of substrate / SiO2 / Cr2O3 from the inside to the outside, forming a composite tritium barrier layer; taking the tritium barrier layer as 100%, the tritium barrier layer is composed according to the following mass percentages: 11.8%≤Cr≤12.2%, 2.46%≤Si≤2.53%, 2.8%≤W≤3.1%, 2.7%≤Al≤3.1%, 0.05%≤Y≤0.06%, Be≤0.5%, and the remaining components are iron and inevitable impurities.

2. The iron-based cladding tritium barrier material for fusion reactor according to claim 1, characterized in that: The Be content in the tritium barrier layer is: 0.1%≤Be≤0.5%.

3. The iron-based cladding tritium barrier material for fusion reactor according to claim 1, characterized in that: The thickness of the tritium barrier layer of the alloy material is 0.11 to 0.872 μm.

4. The iron-based cladding tritium barrier material for fusion reactor according to claim 2, characterized in that: The thickness of the tritium barrier layer of the alloy material is 0.38 to 0.87 μm.

5. A method for preparing the iron-based cladding tritium barrier material for fusion reactor according to claim 1, characterized in that: Here are the steps: a. Using a high-frequency vacuum induction melting process, when the raw materials are batched, the main raw material components are prepared according to the following mass percentage (wt.%) composition: Cr: 11.8~12.2%, Si: 2.46~2.53%, W: 2.8~3.1%, Al: 2.7~3.1%, Y: 0.05~0.06%, Be≤0.5%, and the remaining raw material components are iron and unavoidable impurities. After batching, all the raw materials weighed are subjected to high-frequency vacuum induction melting to obtain an alloy melt, which is then cast to obtain an alloy ingot; b. The alloy ingot prepared in step a is sequentially subjected to hot rolling, warm rolling or cold rolling, annealing and in-situ oxidation processes to finally obtain an iron-based cladding tritium barrier material for a fusion reactor.

6. The method for preparing the iron-based cladding tritium barrier material for fusion reactor according to claim 5, characterized in that: In step a, a high-frequency vacuum induction melting process is used to place the prepared raw materials into a high-frequency vacuum induction furnace and evacuate to 3×10 -3 Pa, and then introduce high-purity argon as a protective gas; then heat it to 1600℃±20℃, and keep it warm for at least 1 minute to obtain an alloy melt, which is then cast into shape.

7. The method for preparing the iron-based cladding tritium barrier material for fusion reactor according to claim 5, characterized in that: In the step b, the alloy ingot obtained by casting the alloy melt prepared in the step a is subjected to hot rolling, wherein the hot rolling temperature is controlled to be not less than 1100° C. and the rolling is repeated at least three times; and then warm rolling is performed, wherein the warm rolling temperature is controlled to be not less than 600° C. and the rolling is repeated at least three times; Then it is subjected to recrystallization annealing treatment and subsequently air-cooled to room temperature; Finally, an in-situ oxidation treatment is carried out in a tubular resistance furnace with openings at both ends. The oxidation temperature is 850°C ± 10°C, and the oxidation atmosphere is a still air atmosphere or a mixed atmosphere of argon and water vapor. The in-situ oxidation process is carried out to finally produce the finished product of the iron-based cladding tritium barrier material for fusion reactors.

8. The method for preparing the iron-based cladding tritium barrier material for fusion reactor according to claim 7, characterized in that: In the step b, when the oxidizing atmosphere is a mixed atmosphere of water vapor, the water vapor is heated in a water bath at 65° C., and is driven by argon gas into the tube furnace to form a mixed atmosphere of water vapor.

9. An application of the iron-based cladding tritium barrier material for a fusion reactor according to claim 1, characterized in that: In a Pb-Li environment of 300-600° C., the iron-based cladding tritium-barrier material for a fusion reactor can be used as a high-temperature resistant and tritium-barrier material, and can also be used as a structural material.

10. The use of the iron-based cladding tritium barrier material for fusion reactor according to claim 9, characterized in that: The iron-based cladding tritium barrier material for a fusion reactor is used as a tritium permeation barrier material in any cladding structure of a fusion reactor reaction.

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