Entropy-controlled BCC alloy having strong resistance to high-temperature neutron radiation damage
11111565 · 2021-09-07
Assignee
- Seoul National University R&DB Foundation (Seoul, KR)
- Korea Institute Of Science And Technology (Seoul, KR)
Inventors
- Eun Soo Park (Suwon-si, KR)
- Hyun Seok Oh (Seoul, KR)
- Il Hwan Kim (Seoul, KR)
- Hye Jung CHANG (Seoul, KR)
- Sangjun Kim (Daegu, KR)
- Chae Woo Ryu (Suwon-si, KR)
Cpc classification
C22C1/0458
CHEMISTRY; METALLURGY
C22C30/00
CHEMISTRY; METALLURGY
C22C27/02
CHEMISTRY; METALLURGY
Y02E30/30
GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
B22F3/105
PERFORMING OPERATIONS; TRANSPORTING
G21C1/02
PHYSICS
G21C13/08
PHYSICS
International classification
C22C30/00
CHEMISTRY; METALLURGY
G21C1/02
PHYSICS
G21C11/08
PHYSICS
C22C27/02
CHEMISTRY; METALLURGY
B22F3/105
PERFORMING OPERATIONS; TRANSPORTING
Abstract
Disclosed is an entropy-controlled solid solution matrix BCC alloy having strong resistance to high-temperature neutron radiation damage. The entropy-controlled solid solution matrix BCC alloy includes three or more multicomponent main elements selected from the element group consisting of Zr, Al, Nb, Mo, Cr, V, and Ti selected based on a neutron absorption cross-sectional area and a mixing enthalpy. Each of the elements is included in an amount of 5 to 35 at %, and the entropy-controlled solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy in a medium-entropy to high-entropy state. In this invention, damage caused by neutron radiation is reduced, and entropy is controlled to thus ensure a solid solution matrix BCC structure having a slow diffusion speed, and accordingly, resistance to void swelling due to radioactive rays is high.
Claims
1. A solid solution matrix BCC alloy consisting of: five elements selected from an element group consisting of Zr, Al, Nb, Mo, V, and Ti, selected based on a neutron absorption cross-sectional area and a mixing enthalpy, wherein four elements of the five elements are Zr, Al, Nb and Ti in the element group, wherein one element of the five elements is Mo or V in the element group, and wherein each of the five elements is included at an equiatomic ratio within an error tolerance limit of 10 at % and the solid solution matrix BCC alloy is a BCC-structure solid solution matrix alloy, which includes multicomponent main elements.
2. The solid solution matrix BCC alloy of claim 1, wherein the one element is Mo in the element group.
3. A fast-breeder reactor comprising: the solid solution matrix BCC alloy of claim 1 as a material for a portion on which neutrons are radiated at a temperature.
4. A method of manufacturing the solid solution matrix BCC alloy of claim 1, the method comprising: an arc-melting step of arc-melting raw materials and then cooling the molten raw materials, or a sintering step of manufacturing the raw materials in a powder form and then sintering the raw materials using spark plasma sintering or hot isostatic pressing at a temperature and a pressure.
5. The method of claim 4, wherein a T.sub.2nd/T.sub.s value, which is obtained by normalizing a precipitation temperature T.sub.2nd of a second phase competing with a solid solution using a solidification temperature T.sub.s, is used to evaluate whether or not the solid solution matrix BCC alloy is formed during preparation of the raw materials.
6. The method of claim 5, wherein whether a single BCC-phase alloy is formed or not is evaluated based on the T.sub.2nd/T.sub.s value of 0.65 or less.
Description
BRIEF DESCRIPTION OF THE DRAWINGS
(1) The above and other objects, features and advantages of the present invention will be more clearly understood from the following detailed description taken in conjunction with the accompanying drawings, in which:
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DESCRIPTION OF THE PREFERRED EMBODIMENTS
(13) Hereinafter, a detailed description will be given of embodiments of the present invention, with reference to the appended drawings.
(14) A novel entropy-controlled BCC alloy having strong resistance to high-temperature neutron damage according to the present invention has a BCC (body-centered cubic) solid solution matrix structure using an entropy-controlled alloy design of elements having a small neutron absorption cross-sectional area even though the alloy is a multicomponent-based alloy including a plurality of main elements, thereby having a property of strong resistance to radiation damage even in a high-temperature radioactive radiation environment. Accordingly, in order to use the entropy-controlled BCC alloy as a structural material for fourth-generation nuclear power systems, which are currently being developed, the following design procedure is performed.
(15) First, Group IV, V, and VI transition elements having a body-centered cubic (BCC) structure are selected as alloy element candidates in order to reduce void swelling, which is a kind of radiation damage and forms voids in metal at high temperatures when radioactive rays are radiated, thus causing the surface of the metal to swell.
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(17) Next, the elements having the small neutron absorption cross-sectional area are selected as the alloy element candidates so as to prevent neutron damage caused by radiation. Generally, the size of the cross-sectional area is used to represent the probability of a reaction occurring between incident particles and an atomic nucleus in a nuclear reaction. Neutrons do not have electric charges and are thus easily brought close to other atomic nuclei, to thus cause various types of interactions. Among the interactions, a cross-sectional area to an absorption reaction of neutrons into a target atomic nucleus is referred to as a neutron absorption cross-sectional area, and is used as a standard in determining reactivity with neutron particles. The neutron absorption cross-sectional area is represented by the number of absorbed neutrons per unit time and unit area, and “barn(b)” is used as the unit of the cross-sectional area. 1 b is 10.sup.−24 cm.sup.2. Generally, the reactivity of the material to the neutron particles is reduced to thus increase resistance to neutron radiation damage as the neutron absorption cross-sectional area of the material is reduced, and accordingly, a material having the small neutron absorption cross-sectional area is suitable as a nuclear material. In the present invention, added elements are designed to be selected from element groups having the small value of 10 or less σa/barns, thereby minimizing the neutron absorption cross-sectional area of the developed material.
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(19) Subsequently, in order to provide the alloy in a high-entropy or medium-entropy state to thus ensure the stable BCC structure at high temperatures and improve mechanical properties at high temperatures using entropy controlling, the elements are selected so as to have a mixing enthalpy (ΔH) of ±15 kJ/mol or less. However, Al, which is the BCC-stabilized element, may have a stable BCC structure even when the mixing enthalpy is high, thus being considered as the constitutional element.
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(21) For a high-entropy alloy (HEA), generally, five or more alloy elements are mixed in an amount of 5 to 35 at % (entropy increases as the amount approaches the equiatomic ratio) to entail high constitutional entropy, thereby forming a unique solid solution rather than an intermetallic compound, which is typically precipitated in a multicomponent-based alloy including a single element as a main component. Further, when the number of alloy elements is 3 to 4, the alloy is in a medium-entropy state and has properties that are similar to those of the high-entropy alloy, depending on the constitutional elements. Since the elements, which are selected in the present invention, have a small mixing enthalpy and a small difference in atomic radius, even the alloys in the medium-entropy state have a stable BCC structure in the solid solution state.
(22) Meanwhile, among the elements having the small neutron absorption cross-sectional area of 10 σa/barns or less, additional elements, such as Be, C, N, O, Si, Sn, P, Fe, Cu, Ni, and Y, or oxides or nitrides thereof, may be added in a small amount of 0.01 to 5 at % to the entropy-controlled BCC solid solution matrix alloy of the present invention to thus entail solid solution hardening or promote precipitation, thereby improving the properties. Particularly, it can be confirmed that the strength of the BCC solid solution is significantly improved when related oxides or nitrides are included in the solid solution matrix.
(23) The alloys of Examples are manufactured, depending on the composition of the present invention, in order to conduct a review, described below, of the properties of the entropy-controlled BCC-structure solid solution matrix alloy having strong resistance to high-temperature neutron radiation damage according to the present invention. The alloys of Comparative Examples, other than the composition of the present invention, are manufactured to compare the present invention and the Comparative Examples to thus confirm the effect of the present invention.
(24) Table 1 shows the representative compositions (Examples) of the present invention and the Comparative Examples in order to confirm whether the entropy-controlled BCC-structure solid solution matrix alloy having strong resistance to high-temperature neutron radiation damage according to the present invention was formed. In the Table, BCC means the body-centered cubic structure, IC means the intermetallic compound, BCC+IC means the state in which the IC is partially precipitated in the BCC solid solution matrix structure, and IC (+ BCC) means a complex structure including the IC, precipitated as the main phase, and the BCC.
(25) TABLE-US-00001 TABLE 1 Sample Composition Crystal structure Comparative Example 1 NbCrTiVCu IC (+BCC) Comparative Example 2 ZrNbCrTiCu IC (+BCC) Comparative Example 3 ZrNbTiFe IC, Unknown phases Comparative Example 4 ZrAlNbTiFe IC, Unknown phases Example 1 ZrTiMo BCC Example 2 ZrNbTi.sub.0.5 BCC Example 3 AlNbTiV BCC Example 4 AlNbTiMo BCC Example 5 ZrNbMoV BCC + IC Example 6 ZrAlNbTi BCC (B2) Example 7 Al.sub.0.5NbTiMoV BCC Example 8 ZrNb.sub.1.5TiMoV BCC Example 9 ZrNbTiMo.sub.0.5V BCC Example 10 ZrNbCr.sub.0.5TiV BCC + IC Example 11 Zr.sub.1.5Nb.sub.1.5TiMoV BCC Example 12 Zr.sub.1.5NbTiMo.sub.0.5V BCC Example 13 ZrNbTiMo.sub.0.33V.sub.0.66 BCC Example 14 ZrAl.sub.0.5NbTiV BCC Example 15 ZrAlNbTiV BCC + IC Example 16 Zr.sub.0.5AlNbTiV BCC Example 17 ZrAlNbTiMo BCC (B2) Example 18 Zr.sub.0.5AlNbTiMoV BCC Example 19 ZrAlNbTiMoV BCC + IC Example 20 ZrAl.sub.0.5NbTiMoV BCC + IC Example 21 ZrAl.sub.0.5NbTiMo.sub.0.5V BCC + IC
(26) An arc-melting process is applied to a method of manufacturing the alloy. Alloy raw materials are melted at high temperatures using Arc plasma and then cooled to manufacture the alloy. The reasons why the arc-melting process is applied in the Examples and the Comparative Examples are that it is easy to form a bulk-type homogeneous solid solution and that the generation of contaminant elements, such as oxides and voids, is minimized, which can be compared to a sintering process. Further, the arc-melting process has a merit in that the ductility-brittleness transition temperature (DBTT) of the composition is relatively lower in the arc-melting process than in the sintering process, thus increasing the rupture time. However, the method of manufacturing the alloy according to the present invention is not limited to the arc-melting process, but the alloy may be manufactured using a commercial casting process, in which raw material metal having a high melting point is melted, and also using high temperature/high pressure sintering, including spark plasma sintering or hot isostatic pressing of raw materials, which are manufactured in a powder form. The sintering process has a merit in that it is easy to control the fine structure and manufacture parts having a desired shape.
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(31) From the drawings, it can be confirmed that the high-entropy BCC alloy, which does not include the intermetallic compound, was formed in all compositions. Accordingly, it can be confirmed that the high-entropy BCC-structure solid solution matrix alloy is manufactured even when the composition of the constitutional element is variously changed within the composition range of 5 to 35%.
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(34) As described above, the entropy-controlled solid solution matrix BCC alloy of the present invention includes an alloy having the entropy-controlled single BCC phase, and additionally includes an alloy that includes a plurality of main elements and the second phase such as the intermetallic compound present in a small amount in the solid solution matrix. Therefore, in the present invention, a T.sub.2nd/T.sub.s value is provided as a forming performance prediction factor for determining the fine structural properties. The T.sub.2nd/T.sub.s value is obtained by normalizing the precipitation temperature T.sub.2nd of the second phase, that is, the intermetallic compound, using a solidification temperature T.sub.s.
(35) Additionally, the entropy-controlled solid solution matrix BCC alloy of the present invention is a kind of high-entropy alloy, which has a thermodynamically meta-stable phase because a high-temperature stable phase is maintained at room temperature, and whether or not the high-entropy solid solution matrix BCC alloy is formed cannot be predicted using a known thermodynamic calculation. However, from the alloy development process, it is confirmed that the temperature range at which the high-entropy solid solution matrix BCC phase is stable is wider in the alloy group having the entropy-controlled single BCC phase than in the solid solution matrix BCC alloy that includes a plurality of main elements and the precipitated second phase, such as the intermetallic compound. This is because the diffusion speed of the atom is increased in the alloy to thus easily precipitate the second phase as the precipitation temperature of the second phase approaches the solidification temperature. Based on the aforementioned description, the T.sub.2nd/T.sub.s value, which is obtained by normalizing the precipitation temperature T.sub.2nd of the second phase using the solidification temperature T.sub.s, is developed as an index of the formation condition of the entropy-controlled solid solution matrix BCC alloy. Particularly, according to the result of measurement of the fine structure in the Examples of the present invention, with regard to the formation performance of the single BCC-phase alloy, the single BCC-phase alloy is formed when the T.sub.2nd/T.sub.s value, which is measured using thermal analysis instruments or is predicted based on thermodynamic calculations and which is obtained by normalizing the precipitation temperature T.sub.2nd of the second phase, such as the intermetallic compound, using the solidification temperature T.sub.s, is 0.65 or less.
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(38) In
(39) Similarly, (c) ZrNbTiFe and (d) ZrAlNbTiFe of
(40) Four or five components are mixed at the equiatomic ratio to manufacture the alloy in the Comparative Examples, which are shown in
(41) Accordingly, even though the multicomponent system includes four or more constitutional elements having large atomic ratios that are similar to each other, the stable BCC-structure solid solution matrix alloy is not formed in all types of multicomponent systems, but is formed based on the basic premise that the mixing enthalpy difference is small (ΔH.sub.mix=±15 kJ/mol or less).
(42) Therefore, it can be confirmed that the ternary to senary alloys of the present invention have the stable single-phase BCC structure.
(43) Although the preferred embodiments of the present invention have been disclosed for illustrative purposes, those skilled in the art will appreciate that various modifications, additions and substitutions are possible, without departing from the scope and spirit of the invention as disclosed in the accompanying claims.