CN116121613A - Beryllium-zirconium alloy and application thereof in nuclear fusion - Google Patents

Beryllium-zirconium alloy and application thereof in nuclear fusion Download PDF

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CN116121613A
CN116121613A CN202211648859.4A CN202211648859A CN116121613A CN 116121613 A CN116121613 A CN 116121613A CN 202211648859 A CN202211648859 A CN 202211648859A CN 116121613 A CN116121613 A CN 116121613A
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beryllium
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刘平平
詹倩
万发荣
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University of Science and Technology Beijing USTB
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
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    • C22C25/00—Alloys based on beryllium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
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Abstract

The invention relates to a beryllium-zirconium alloy and application thereof in nuclear fusion, the beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate, wherein the atomic percentage expression of the components of the beryllium-zirconium alloy is Be a (Zr b M c )X d Wherein M is one or more of Y, ti, V, mn, fe, mg, cr, co, W, mo, nb, pb, bi, ta, hf, tl and Re, X is one or more of O, C, N, P, S, si, al, ca, sc, ni, cu and U, a is 65-a-97,3-b-35, C is 0-35 and 0<d is less than or equal to 3, and a+b+c+d=100. The beryllium-zirconium alloy has the advantages of large component range, wide preparation conditions, excellent high-temperature performance, melting point exceeding 1800 ℃, neutron proliferation rate approaching 1, excellent anti-irradiation swelling performance and mechanical property.

Description

Beryllium-zirconium alloy and application thereof in nuclear fusion
Technical Field
The invention belongs to the field of metal materials, and particularly relates to beryllium-zirconium alloy and application thereof in nuclear fusion.
Background
With the addition of China to the International thermonuclear fusion experimental reactor (ITER) project, nuclear fusion energy is becoming an internationally recognized clean energy source and gradually enters the field of view of people. However, the implementation of commercial controlled nuclear fusion still faces 3 major bottleneck problems, one of which is the self-sustaining problem of fusion tritium fuel. And neutron breeder materials are one of the keys to solve this bottleneck problem.
Beryllium is an excellent neutron breeder material. The neutron of beryllium has small binding energy (1.666 MeV) in the atomic nucleus, which is equivalent to 1/5-1/6 of most stable atomic energy, and the neutron is easy to release through the reactions including (n, 2 n) of high-energy particle bombardment, so that the proliferation of the neutron is realized. The metallic beryllium, with a transmutation He injection amount below 3000app m and with no obvious irradiation swelling (< 3%), was selected as neutron breeder in the ITER nuclear fusion reactor cladding below 400 ℃. However, the commercial controllable fusion reactor (DEMO) in the future is more harsh in environment, the operation temperature is higher (600-900 ℃), the irradiation dose is larger, the helium injection amount is up to 20000app m, the irradiation swelling of beryllium is particularly obvious (> 3%), and the operation of the reactor can be endangered.
Intermetallic compounds of beryllium, e.g. Be 12 Ti attracts attention of researchers, and especially Japanese vs Be 12 Ti was studied extensively. However, due to the addition of Ti, be 12 The neutron multiplication performance of Ti is greatly reduced, and the toughness is poor, so that the production and the use of alloy and neutron multiplication agent pellets are extremely unfavorable. Therefore, research on new alloys with higher toughness and higher neutron breeder properties is of great importance in the field of fusion neutron breeder and even in the field of high temperature.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention provides a beryllium-zirconium alloy and application thereof in nuclear fusion, which are used for solving the problems in the prior art.
A beryllium-zirconium alloy comprises the following components in percentage by atom a (Zr b M c )X d Wherein M is one or more of Y, ti, V, mn, fe, mg, cr, co, W, mo, nb, pb, bi, ta, hf, tl and Re, X is one or more of O, C, N, P, S, si, al, ca, sc, ni, cu and U, a is 65-a-97,3-b-35, C is 0-35 and 0<d is less than or equal to 3, and a+b+c+d=100.
In the aspect and any one of the possible implementation manners described above, there is further provided an implementation manner that when 0<d is equal to or less than 2,0 is equal to or less than c is equal to or less than 3.57, c is equal to or less than 7.15,91 is equal to or less than a is equal to or less than 97, the beryllium zirconium alloy comprises a face-centered cubic structure phase and a close-packed hexagonal structure phase, and the grain size is equal to or less than 80um.
In the aspects and any possible implementation manner, there is further provided an implementation manner, when 0<d is less than or equal to 2,0 is less than or equal to c is less than or equal to 5.25, c is less than or equal to 10.53,87.72 is less than or equal to a is less than or equal to 92.86, the beryllium zirconium alloy comprises a face-centered cubic structure phase and a three-way structure or tetragonal structure phase, and the grain size is less than or equal to 80um.
In the aspect and any possible implementation manner, when 0<d is less than or equal to 2,0 is less than or equal to c is less than or equal to 8.33, c is less than or equal to 16.34,81.7 is less than or equal to a is less than or equal to 89.48, the beryllium zirconium alloy comprises a three-way structure phase and a hexagonal structure phase or a tetragonal structure phase, and the grain size is less than or equal to 80um.
In the aspect and any possible implementation manner, when 0<d is less than or equal to 2,0 is less than or equal to c is less than or equal to 8.33, c is less than or equal to 16.34,65 is less than or equal to a is less than or equal to 83.34, the beryllium zirconium alloy comprises a three-way structure phase, a hexagonal structure phase, a tetragonal structure phase and a face-centered cubic structure phase, and the grain size is less than or equal to 80um.
In the aspect and any possible implementation manner as described above, there is further provided an implementation manner, where when d=1.55, c=0.1, b=7.5a=90.85, the atomic percentage expression of the beryllium zirconium alloy is Be 90.85 Zr 7.5 M 0.1 X 1.55 The beryllium-zirconium alloy comprises a face-centered cubic structure phase and a tetragonal structure phase, and the grain size is less than or equal to 80um.
In the aspects and any possible implementation manner described above, there is further provided an implementation manner, wherein the melting point of the beryllium-zirconium alloy is greater than 1800 ℃, and the neutron multiplication rate is close to 1.
In the aspect and any possible implementation manner described above, there is further provided an implementation manner, where when d=1.86, c=1.22, b=5.79, and a= 91.13, the atomic percentage expression of the beryllium-zirconium alloy is Be 91.13 Zr 5.79 M 1.22 X 1.86 The alloy is of a face-centered cubic structure, and the grain size is less than or equal to 80 mu m.
In the aspect and any possible implementation manner as described above, there is further provided an implementation manner, where when d=1.61, c=0.08, b=8.28, and a=90.03, the atomic percentage expression of the beryllium zirconium alloy is Be 90.03 Zr 8.28 M 0.08 X 1.61 Comprising a face-centered cubic structure, a tetragonal structure phase and three phasesSquare structure phase, grain size is less than or equal to 80um.
The invention also provides application of the beryllium-zirconium alloy in a neutron breeder for nuclear fusion stacks.
The beneficial effects of the invention are that
Compared with the prior art, the invention has the following beneficial effects:
the invention relates to a beryllium-zirconium alloy with high temperature, high toughness and high neutron multiplication rate, wherein the atomic percentage expression of the components of the beryllium-zirconium alloy material is Be a (Zr b M c )X d Has the following advantages:
1. beryllium zirconium alloys have a large composition range and wide preparation conditions.
2. The phase composition, grain refinement and the like can be controlled by adjusting alloy components, heat treatment, cold and hot processing technology and the like, so that different high-temperature performances, mechanical performances and neutron proliferation performances can be obtained.
3. The main elements of the beryllium-zirconium alloy material with high temperature, high toughness and high neutron proliferation rate provided by the invention are general metal raw materials and compounds, and can be prepared by different preparation methods, and the beryllium-zirconium alloy material has the advantages of convenience in preparation, simple process, economy and the like.
4. The beryllium-zirconium alloy prepared by the invention has excellent high-temperature performance, the melting point is over 1800 ℃, the neutron proliferation rate can be close to 1 (i.e. less than or equal to 1), and the irradiation swelling resistance and the mechanical property are excellent.
5. The beryllium-zirconium alloy provided by the invention has excellent mechanical property, high-temperature property, excellent anti-irradiation swelling property and neutron multiplication property, and can be widely applied to the neutron multiplication field, the plasma-oriented material field and the high-temperature material field.
Drawings
FIG. 1 is an X-ray diffraction pattern of a beryllium zirconium alloy of example 1 of the present invention;
FIG. 2 is a microstructure of the beryllium zirconium alloy of example 2 of the present invention.
Detailed Description
For a better understanding of the present invention, the present disclosure includes, but is not limited to, the following detailed description, and similar techniques and methods should be considered as falling within the scope of the present protection. In order to make the technical problems, technical solutions and advantages to be solved more apparent, the following detailed description will be given with reference to the accompanying drawings and specific embodiments.
It should be understood that the described embodiments of the invention are only some, but not all, embodiments of the invention. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to be within the scope of the invention.
The terminology used in the embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. As used in this application and the appended claims, the singular forms "a," "an," and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise.
The invention relates to a beryllium-zirconium alloy with high temperature, high toughness and high neutron multiplication rate, wherein the atomic percentage expression of the components of the beryllium-zirconium alloy material is Be a (Zr b M c )X d Wherein M is one or more of Y, ti, V, mn, fe, mg, cr, co, W, mo, nb, pb, bi, ta, hf, tl and Re, X is one or more of O, C, N, P, S, si, al, ca, sc, ni, cu and U, a is 65-a-97,3-b-35, C is 0-35 and 0<d is less than or equal to 3, and a+b+c+d=100.
The beryllium-zirconium alloy of the invention utilizes neutron multiplication nuclides such as Be, zr and the like, refractory metal elements with large-size atoms, low-activation elements such as Zr, W, Y and the like, auxiliary phases such as Be 92.86 Y 7.14 And the like, the beryllium-zirconium alloy with the characteristics of high temperature and high neutron multiplication rate is obtained and is applied to neutron multiplication agent materials for fusion stacks, and structural and functional materials facing plasmas and in other high-temperature environments.
Further, when 0<d is less than or equal to 2, c is less than or equal to 0 and less than or equal to 3.57, c is less than or equal to 7.15,91 and a is less than or equal to 97, the beryllium-zirconium alloy can be composed of a face-centered cubic structure and a close-packed hexagonal structure, the grain size is less than or equal to 80um, and the beryllium-zirconium alloy has excellent toughness and high neutron proliferation rate.
Further, when d=1.86, c=1.22, b=5.79, a= 91.13, what is said isThe atomic percentage expression of the beryllium-zirconium alloy is Be 91.13 Zr 5.79 M 1.22 X 1.86 The alloy is of a face-centered cubic structure, has the grain size of less than or equal to 80 mu m, and has high neutron proliferation rate, excellent toughness, high-temperature performance, tritium retention and irradiation swelling resistance.
Further, when 0<d is less than or equal to 2, c is less than or equal to 0 and less than or equal to 5.25, c is less than or equal to 10.53,87.72 and a is less than or equal to 92.86, the beryllium-zirconium alloy can be composed of a face-centered cubic structure phase and a three-way structure phase or a tetragonal structure phase, the grain size is less than or equal to 80um, and the beryllium-zirconium alloy has excellent high-temperature performance, tritium retention and anti-irradiation swelling performance.
Further, when d=1.55, c=0.1, b=7.5a=90.85, the atomic percent expression of the beryllium zirconium alloy is Be 90.85 Zr 7.5 M 0.1 X 1.55 The alloy consists of a face-centered cubic structure and a tetragonal structure, has a grain size less than or equal to 80 mu m, and has excellent toughness, processability, tritium retention and irradiation swelling resistance.
Further, when d=1.61, c=0.08, b=8.28, a=90.03, the atomic percent expression of the beryllium zirconium alloy is Be 90.03 Zr 8.28 M 0.08 X 1.61 The alloy consists of a face-centered cubic structure, a tetragonal structure and a three-way structure phase, has the grain size of less than or equal to 80 mu m, and has better toughness, excellent high-temperature performance, tritium retention and anti-irradiation swelling performance.
Further, when 0<d is less than or equal to 2, c is less than or equal to 0 and less than or equal to 8.33, c is less than or equal to 16.34,81.7 and a is less than or equal to 89.48, the beryllium-zirconium alloy can be composed of a three-way structure and a hexagonal or tetragonal structure, the grain size is less than or equal to 80um, and the beryllium-zirconium alloy has higher neutron proliferation rate, excellent high-temperature performance, tritium retention performance and anti-irradiation swelling performance.
Further, when 0<d is less than or equal to 2, c is less than or equal to 0 and less than or equal to 8.33, c is less than or equal to 16.34,65 and a is less than or equal to 83.34, the beryllium-zirconium alloy can be composed of a three-way structure phase, a hexagonal structure phase, a tetragonal structure phase and a face-centered cubic structure phase, the grain size is less than or equal to 80um, and the beryllium-zirconium alloy has excellent high-temperature performance, tritium retention and irradiation swelling resistance.
A method of preparing the beryllium zirconium alloy of the present invention will now be described.
The beryllium-zirconium alloy and the preparation method for preparing the neutron multiplier beryllium-zirconium alloy pellets by using the beryllium-zirconium alloy are realized by adopting a hot isostatic pressing method, a plasma sintering method, a rotating electrode method or a powder metallurgy method.
The preparation method of the beryllium-zirconium alloy by adopting the hot isostatic pressing method comprises the following steps:
s1, proportioning pure beryllium powder, titanium powder and other raw materials according to the chemical composition ratio;
s2, mixing the metal powder in proportion, filling the mixture into a cladding for high-vacuum sealing welding, and placing the metal cladding for wrapping the metal powder into a hot isostatic pressing device together for pressing into ingots by adopting a hot isostatic pressing method. The production conditions at this time were as follows:
pressure intensity: 60-1000 MPa of the pressure-sensitive adhesive,
temperature: 300-1200 ℃,
time: and 0.5 to 6 hours.
The preparation method of the beryllium-zirconium alloy by the plasma sintering method comprises the following steps:
s1, proportioning pure beryllium powder, titanium powder and other raw materials according to the chemical composition ratio;
s2, mixing the metal powder in proportion, and then carrying out vacuum plasma rapid sintering and forming. The sintering conditions at this time are described as follows:
vacuum degree: 1X 10 -1 pa～1×10 -10 Pa temperature: 300-1300 DEG C
Time: 0.5 to 6 hours
Powder metallurgy method:
the neutron multiplication agent beryllium zirconium alloy microsphere is manufactured by the method, the neutron multiplication material beryllium zirconium alloy prepared by the method is firstly used as a material, and then the material is put into a die, crushed and spheroidized to obtain the neutron multiplication agent beryllium zirconium alloy microsphere.
Rotary electrode method:
the beryllium-zirconium alloy microsphere of the neutron breeder is prepared by a rotating electrode method, the beryllium-zirconium alloy prepared by the method is firstly prepared into a consumable electrode beryllium-zirconium alloy rod, and the beryllium-zirconium alloy can be mechanically processed to prepare a specified electrode shape as a consumable electrode; then, the neutron breeder beryllium zirconium alloy microsphere was produced by a rotary electrode method using the prepared consumable electrode. The production conditions in this case are not particularly limited, and the following description is given regarding preferable conditions:
atmosphere gas pressure of 60MPa to 1100MPa
Arc current of 100-1000A
The rotation speed of the consumable electrode is 5-1000 m/s
[ example ]
Example 1
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: be:90.03at.%, 8.28at.% Zr, 1.03at.% O, 0.08at.% Fe, and the total content of other elements including O, C, N, P, S, si, al, ca, sc, ni, cu, U is 0.58at.%, and is prepared by hot isostatic pressing at 1000 ℃ for 1.5 hours, as shown in figure 1, the alloy is formed by a face-centered cubic structure Be 92.86 Zr 7.14 Three-phase structure Be 89.47 Zr 10.53 The phase and close-packed hexagonal structure Be phase are composed, the average grain size is less than or equal to 80um, the neutron proliferation rate is as high as 0.93, the nano indentation hardness is 2.5GPa, the processing performance and the fracture toughness are excellent, the performance is shown in Table 1, and the alloy is particularly suitable for the neutron proliferation field and the high temperature field.
TABLE 1
Figure BDA0004011052690000091
The properties in Table 1 are described as follows:
the neutron multiplication performance is the neutron multiplication performance of the elements constituting the alloy, and is evaluated by the neutron multiplication rate, and because beryllium is a naturally excellent neutron multiplication material, beryllium is used as a contrast material (the neutron multiplication rate is 1), and the closer the other material performance is to 1, the better the neutron multiplication performance is.
Tritium retention performance (which is a method for testing the performance of a material, specifically, tritium is injected into the material, and then the retention of the tritium in the material is measured), and because the purpose of the fusion neutron breeder is to realize the self-sustaining of tritium fuel, the retention of the tritium in the material is also important, and the tritium retention condition is measured by adopting a temperature rising analysis gas analyzer (TDS). That is, the tritium is retained in a good manner (little retention), in a medium manner (retained portion), and in a poor manner (much retention).
The anti-irradiation swelling performance is that the neutron irradiation material can generate a large number of vacancies, the vacancies further migrate and aggregate to form vacancy clusters such as holes, the volume of the material is swelled, the irradiation swelling rate of the metallic beryllium is more than 3 percent under the condition that the helium injection amount is 3000app m at the high temperature of 400 ℃, the safe operation of the reactor is endangered, the anti-swelling performance is poor, and the irradiation swelling rate is 1-3 percent by taking the anti-irradiation swelling performance as a comparison, and is better than 1 percent by taking the anti-swelling performance as a comparison.
Other properties are well known in the art and will not be specifically described. Due to the differences of material components, heat treatment process, cold and hot processing process and the like, the phase composition, grain size and the like of the material are different, so that various properties of the material are regulated and controlled. The alloy of the number 1 in Table 1, which comprises beryllium and titanium, is annealed appropriately to give a single phase Be 92.31 Ti 7.69 The single phase is tetragonal structure phase, and the measured seed proliferation rate is 0.92, the tritium retention performance is excellent, but the fracture toughness and the processing performance are particularly poor, and the later balling rate is particularly low, so that the application of the single phase is severely limited. The invention takes beryllium and zirconium as main elements, is assisted by Y, fe and other elements, utilizes neutron multiplication nuclides such as Be, zr, refractory metal elements with large-size atoms, doping of low-activation elements such as Y and the like, and assisted phases such as Be 92.31 Fe 7.69 The grain size of the material is controlled by combining the processes, so that the neutron proliferation rate, toughness, high-temperature performance and other performances of the beryllium-zirconium alloy are improved.
Example 2
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: be:90.03at percent of Zr, 8.28at percent of O, 1.03at percent of Fe, 0.08at percent of other elements including O, C, N, P, S, si, al, ca, sc, ni, cu and U totally contain 0.58at percent, the alloy is sintered by adopting vacuum plasma, the temperature is 800 ℃ and the time is 1h, as shown in figure 2, and the atomic percentage expression of the alloy is Be 90.03 Zr 8.28 M 0.08 X 1.61 The alloy consists of a face-centered cubic structure Be 92.86 Zr 7.14 Three-party structure Be 89.47 Zr 10.53 And close-packed hexagonal structure Be phase, the average grain size is less than or equal to 80um, the neutron proliferation rate is as high as 0.93, the nano indentation hardness is 2.42GPa, the processability and fracture toughness are excellent, the performance data are shown in Table 1, and the alloy is applicable to the neutron proliferation field and the high temperature field.
Example 3
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: be:90.85at.%, 7.5at.% Zr, 0.98at.% O, 0.1at.% Fe, other elements including O, C, N, P, S, si, al, ca, sc, ni, cu, U total 0.57at.%, sintered by hot isostatic pressing or plasma, and then annealed at 1200 ℃ for 2 hours, the alloy consisting of face-centered cubic structure Be 92.86 Zr 7.14 And very small amount of tetragonal Be 92.31 Fe 7.69 The phase composition, average grain size less than or equal to 80um, performance data are shown in Table 1, neutron proliferation rate>0.93, the nano indentation hardness is 2.6GPa, and the high temperature, toughness and anti-irradiation swelling performance are excellent, which indicates that the alloy can be applied to the neutron proliferation field and the high temperature field.
Example 4
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: be:91.13at.%, 5.79at.% Zr, 1.22 at.% Y, and other elements including O, C, N, P, S, si, al, ca, sc, ni, cu, and U with a total content of 1.86at.% and an atomic percentage expression of Be 91.13 Zr 5.79 Y 1.22 X 1.86 The alloy is prepared by adopting a hot isostatic pressing method or a plasma sintering method, is annealed for 2 hours at 1200 ℃, and is formed by a face-centered cubic structure Be 92.86 Zr 7.14 And Be 92.86 Y 7.14 The phase composition, average grain size is less than or equal to 80um, melting point is as high as 1800-1920 ℃, the performance data is shown in table 1, neutron proliferation rate is 0.93, processability and fracture toughness are excellent, and the alloy is applicable to neutron proliferation field, face-centered plasma material field and high temperature field.
Example 5
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: 90.01at percent of Be, 5.22at percent of Zr, 2.1at percent of Y, 1.12at percent of V, and other elements including O, C, N, P, S, si, al, ca, sc, ni, cu and U with total content of 1.62at percent are prepared by adopting a hot isostatic pressing method to obtain the beryllium-zirconium multicomponent alloy, the average grain size is less than or equal to 80um, the melting point is as high as 1800 ℃, the performance data is shown in the table 1, the neutron proliferation rate is 0.92, and the toughness and the anti-irradiation swelling performance are excellent, so that the alloy can Be suitable for the neutron proliferation field and the high-temperature field.
Example 6
A beryllium-zirconium alloy with high temperature, high toughness and high neutron proliferation rate comprises the following components: be:90.0at percent of Zr, 6.2at percent of Ti, 1.18at percent of V, 1.1at percent of V, and other elements including O, C, N, P, S, si, al, ca, sc, ni, cu and U with total content of 1.52at percent are prepared by adopting an ion sintering method to obtain the beryllium-zirconium multicomponent alloy, the average grain size is less than or equal to 80um, the performance data are shown in table 1, the neutron proliferation rate is 0.92, the irradiation swelling resistance and the tritium retention performance are excellent, and the alloy is applicable to the neutron proliferation field and the high-temperature field.
While the foregoing description illustrates and describes the preferred embodiments of the present invention, it is to be understood that the invention is not limited to the forms disclosed herein, but is not to be construed as limited to other embodiments, and is capable of numerous other combinations, modifications and environments and is capable of changes or modifications within the scope of the inventive concept as expressed herein, either as a result of the foregoing teachings or as a result of the knowledge or technology of the relevant art. And that modifications and variations which do not depart from the spirit and scope of the invention are intended to be within the scope of the appended claims.

Claims (10)

1. A beryllium-zirconium alloy is characterized in that the atomic percentage expression of the components of the beryllium-zirconium alloy material is Be a (Zr b M c )X d Wherein M is one or more of Y, ti, V, mn, fe, mg, cr, co, W, mo, nb, pb, bi, ta, hf, tl and Re, X is one or more of O, C, N, P, S, si, al, ca, sc, ni, cu and U, a is 65-a-97,3-b-35, C is 0-35 and 0<d is less than or equal to 3, and a+b+c+d=100.
2. The beryllium zirconium alloy of claim 1, wherein the beryllium zirconium alloy comprises face-centered cubic structured phases and close-packed hexagonal structured phases with grain size of 80um or less when 0<d c is 2 or less, 0 c is 3.57 or less, c < b is 7.15,91 a is 97 or less.
3. The beryllium zirconium alloy according to claim 1, wherein the beryllium zirconium alloy comprises a face-centered cubic structure phase and a trigonal or tetragonal structure phase with a grain size of 80um or less when 0<d c.ltoreq.2, 0.ltoreq.c.ltoreq.5.25, c.ltoreq. 10.53,87.72.ltoreq.a.ltoreq.92.86.
4. The beryllium zirconium alloy according to claim 1, wherein when 0<d is 2 or less, c is 0 or less and 8.33 or less, c < b is 16.34,81.7 or less and a is 89.48 or less, the beryllium zirconium alloy comprises a three-sided structural phase and a hexagonal structural phase or a tetragonal structural phase, and the grain size is 80um or less.
5. The beryllium zirconium alloy of claim 1, wherein when 0<d is 2 or less, c is 0 or less and 8.33 or less, c < b is 16.34,65 or less and a is 83.34 or less, the beryllium zirconium alloy comprises a trigonal phase, a hexagonal phase, a tetragonal phase, and a face-centered cubic phase, and the grain size is 80um or less.
6. The beryllium zirconium alloy of claim 1, wherein when d = 1.55, c = 0.1, b = 7.5a = 90.85, the atomic percent expression of the beryllium zirconium alloy is Be 90.85 Zr 7.5 M 0.1 X 1.55 The beryllium-zirconium alloy comprises a face-centered cubic structure phase and a tetragonal structure phase, and the grain size is less than or equal to 80um.
7. The beryllium zirconium alloy of claim 1, wherein the beryllium zirconium alloy has a melting point greater than 1800 ℃ and a neutron propagation rate approaching 1.
8. The beryllium zirconium alloy according to claim 1, wherein when d=1.86, c=1.22, b=5.79, a= 91.13, the atomic percent expression of the beryllium zirconium alloy is be91.13zr5.79m1.22x1.86, the alloy has a face-centered cubic structure, and the grain size is equal to or less than 80um.
9. The beryllium zirconium alloy of claim 1, wherein when d = 1.61, c = 0.08, b = 8.28, a = 90.03, the beryllium zirconium alloy has an atomic percent expression of be90.03zr8.28m0.08x1.61, including face-centered cubic, tetragonal, and trigonal phases, with a grain size of 80um or less.
10. Use of the beryllium-zirconium alloy of any of claims 1-9 in a neutron breeder for nuclear fusion stacks.
CN202211648859.4A 2022-12-21 2022-12-21 Beryllium-zirconium alloy and application thereof in nuclear fusion Pending CN116121613A (en)

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