Matheus A.
Tunes
*a,
Graeme
Greaves
b,
Philip D.
Rack
cd,
Walker L.
Boldman
d,
Cláudio G.
Schön
e,
Stefan
Pogatscher
f,
Stuart A.
Maloy
a,
Yanwen
Zhang
dg and
Osman
El-Atwani
a
aMaterials Science and Technology Division, Los Alamos National Laboratory, USA. E-mail: tunes@lanl.gov
bSchool of Computing and Engineering, University of Huddersfield, UK
cJoint Staff Center of Nanophase Materials Sciences, Oak Ridge National Laboratory, USA
dMaterials Science and Engineering Department, University of Tennessee, USA. E-mail: yzhang1@ornl.gov
eDepartment of Metallurgical and Materials Engineering, Escola Politécnica, Universidade de São Paulo, Brazil
fChair of Nonferrous Metallurgy, Montanuniversitaet Leoben, Austria
gMaterials Science and Technology Division, Oak Ridge National Laboratory, USA
First published on 3rd December 2021
In the field of radiation damage of crystalline solids, new highly-concentrated alloys (HCAs) are now considered to be suitable candidate materials for next generation fission/fusion reactors due to recently recorded outstanding radiation tolerance. Despite the preliminarily reported extraordinary properties, the mechanisms of degradation, phase instabilities and decomposition of HCAs are still largely unexplored fields of research. Herein, we investigate the response of a nanocrystalline CoCrCuFeNi HCA to thermal annealing and heavy ion irradiation in the temperature range from 293 to 773 K with the objective to analyze the stability of the nanocrystalline HCA in extreme conditions. The results led to the identification of two regimes of response to irradiation: (i) in which the alloy was observed to be tolerant under extreme irradiation conditions and (ii) in which the alloy is subject to matrix phase instabilities. The formation of FeCo monodomain nanoparticles under these conditions is also reported and a differential phase contrast study in the analytical electron-microscope is carried out to qualitatively probe its magnetic properties.
A major goal in metallurgy is the design of new metallic alloys that combine superior strength and ductility with enhanced physico–chemical properties. After synthesis and specific processing, polycrystalline metallic alloys have grain sizes within the microscale which will then define the set of macroscopic properties associated with their final application. Historically, the properties of metallic alloys can be tailored by controlling their final microstructure parameters. In this sense, the emergence of nanometallurgy embraces new strategies aimed at reducing the grain-size of metallic alloys towards the nanoscale, presumably resulting in an enhancement of a wide variety of physical and mechanical properties. This has yielded unprecedented gains for the design of future metallic alloys.14,15
It is well known that nanograins (<100 nm) are able to hinder the glide of dislocations during deformation processes, directly leading to higher strength when compared with micrometre-sized grains in conventional alloys.16–22 A particular field of technology where the potential application of nanocrystalline alloys has been under active consideration is in the selection of appropriate structural materials for the next generation of fission and fusion reactors, by mitigating the generation and by controlling the diffusion of crystal defects at the nanoscale.23–31 An increased density of grain boundaries acting as active sinks for crystalline defects produced from energetic collisions has been recently reported to be the main reason of enhanced radiation resistance of many metals and alloys when compared with their coarse-grained alloy counterparts.26–28
The major challenge for application of nanocrystalline materials in extreme environments remains to prevent the manifestation of degradation mechanisms resulting in microstructural instabilities such as grain growth24,26,30–36 and phase transformations.37–42 In order to do so, the nanocrystalline idea has been recently combined with the HCA concept.4–6,43 Recent research indicated these emergent equiatomic metallic alloys can exhibit improved levels of radiation resistance when compared with conventional nuclear materials such as Zr- and Fe-based alloys.19,26,27,35,41,44–47 With respect to the application of HCAs as nuclear materials, some challenges are still pending when it comes to their radiation response: phase stability at high temperature irradiation7,48,49 and, in addition, the occurrence of radiation-induced precipitation and segregation (RIP/RIS).28
Degradation, phase transformations, segregation and precipitation studies on HCAs are still limited, but some recent works have addressed this problem. Santodonato et al.50 investigated the influence of small Al additions in the high-temperature response of the CoCrCuFeNi HCA. The synthesized alloy had large grains in the mesoscale (“hundreds of microns” according to the authors50). They reported the occurrence of a distinct spinodal decomposition of the alloy matrix phase into several classes of CoCrFe-rich BCC (B2) nanoprecipitates and Cu-partition, although concluding that the characteristic disorder of HCA system is preserved given the distribution of multiple elements in both detected secondary phases and remaining matrix. Similar results were obtained by Xu et al.51 working with the same alloy system with grain sizes still in the mesoscale ranging from 100 nm to 1.8 μm. Similarly to Santodonato et al.,50 Xu et al. also reported on Cu-partition from the alloy matrix and also the formation of ordered FeCoCr(Ni)-rich domains upon annealing.
These works serve as motivation for further studies to investigate whether nanocrystallinity can help HCAs to prevent degradation and phase transformations either under high-temperature annealing or energetic particle irradiation.
A fundamental study on the metallurgical phase stability under annealing and heavy-ion irradiation of a nanocrystalline HCA was carried out in this work. The main objectives of this present work are to investigate the response of the nanocrystalline alloy when subjected to the extreme conditions. Although nanocrystalline alloys are widely studied today, the mechanisms by which they degrade upon irradiation and also annealing – e.g. grain growth and phase transformations – are largely unknown.36 For this, an equiatomic CoCrCuFeNi alloy – which is a modified version of the classical Cantor's alloy1,2 (CoCrMnFeNi) – was subjected to thermal annealing and heavy ion irradiation in situ within a TEM over a wide range of temperatures. The alloy was pre- and post-irradiation characterised using energy dispersive X-ray spectroscopy (EDX) and differential phase contrast (DPC) within a scanning transmission electron microscope (STEM). In addition, a detailed study on grain growth during both irradiation and annealing was carried out using selected area diffraction (SAED) and bright-field transmission electron microscopy (BFTEM). The results shed light that in the regime where the diffusion of vacancies is limited (298–573 K), grain growth is prevented due to the solute drag effect along the interfaces. In the regime where vacancies are mobile (T > 573 K), the alloy transforms to another state with the observation of a magnetic nanophase composed of Fe and Co. It is demonstrated that by simply replacing Mn by Cu in a well-known HCA system, the thermodynamic stability – presumed to be high for HCAs – can be disrupted, but gives rise to the formation of a potential functional material composed of monodomains with high magnetization saturation at the nanoscale.
The SAED patterns corresponding to the BFTEM micrographs in Fig. 1 are shown in Fig. 2 as a function of both irradiation temperature and dose. By analysing the BFTEM micrographs (Fig. 1) and SAED patterns (Fig. 2), grain growth occurred extensively at the irradiation temperature of 773 K whilst at both 293 K and 573 K, the grain growth was more modest. In the SAED patterns in Fig. 2, grain growth is noted when the polycrystalline ring-patterns start to exhibit well defined and distinct Bragg-reflection spots.
Fig. 2 Crystallographic response to irradiation. Diffraction patterns indexed with FCC structure35 and recorded during (a) thermal annealing and (b–e) the in situ TEM heavy ion irradiation experiments at 293, 573 and 773 K and corresponding to the areas shown in the BFTEM micrographs in Fig. 1. |
dn(Φ) = dn0 + KΦ | (1) |
Fig. 3 Microstructural kinetics analysis. The plot shows the evolution of the nanocrystalline grain sizes as function of the irradiation dose at 293, 573 and 773 K. |
In the eqn (1), d0 is the average grain size prior to irradiation and annealing and K is a constant related with the grain boundary mobility.33 In the theoretical model presented in eqn (1), both K and n are fitting parameters directly dependent on the material under investigation and the annealing or irradiation temperature. The results shown in Fig. 3 follow those exhibited by Fig. 1: as the irradiation dose increases, small grain growth is observed for the irradiations at 293 and 573 K whilst the grains grew faster and larger for the irradiation at 773 K. As the samples were annealed during 30 min at both 573 and 773 K prior to irradiation, the first data points (at 0 dpa) for both blue and green curves in the Fig. 3 represent a small grain growth solely due to annealing, therefore, the grain growth herein reported is due to the effects of ion irradiation.
By fitting the average grain sizes as function of irradiation dose and temperature, it was possible to estimate the non-linear fitting parameters n and K. The results of the fittings are summarized in Table 1.
d n (Φ) = dn0 + KΦ | 293 K | 573 K | 773 K |
---|---|---|---|
d 0 [nm] | 11.4 | 12.3 | 14.3 |
K m [nmn dpa−1] | 1.4 × 108 | 1.0 × 109 | 1.6 × 104 |
n | 7.3 | 7.7 | 3.2 |
R 2 | 90% | 99% | 97% |
Element | Atomic fraction [%] |
---|---|
Co | 17.5 ± 2.1 |
Cr | 17.7 ± 2.9 |
Cu | 20.3 ± 3.4 |
Fe | 18.7 ± 3.1 |
Ni | 25.8 ± 4.3 |
No significant modifications were observed for the irradiation experiments at both 293 K (Fig. 4 (row a)) and 573 K (Fig. 4 (row b)): the alloy has neither experienced a phase transformation nor elemental segregation as a result of irradiation. The irradiation case at 573 K exhibits segregation of Xe along the voided grain boundaries of the sub-grains, although no Xe bubbles were observed for the irradiations up to 11 dpa at both 293 and 573 K. Fig. 5(a) shows an overlay between a bright-field micrograph and Cr elemental map of the alloy irradiated up to 11 dpa at 573 K. The corresponding elemental quantification profile in Fig. 5(b) indicates enrichment of Cr along the grain boundaries of the nanocrystalline CoCrCuFeNi HCA.
On the irradiation response of the nanocrystalline CoCrCuFeNi HCA, chemical and thermodynamic phase instabilities were observed only for the irradiation at 773 K. Alterations in the local alloy chemistry at this irradiation temperature is shown in Fig. 4 (row c). As demonstrated for this irradiation case, large Xe bubbles were observed within the microstructure of the alloy (diameters between 20–60 nm as clearly exhibited in the Xe elemental map in Fig. 4 (row c). Cr segregates from the HCA single phase matrix random solid solution and it is observed to be completely segregated from the other constituents of the alloy. After irradiation at 773 K, annealing at this temperature was performed and Cr was reincorporated to the solid solution as observed in Fig. 4 (row d). Annealing after irradiation also led to the nucleation of a secondary phase rich in FeCo with a particular spherical-shape morphology. In addition, Xe bubbles were not visible after annealing the irradiated microstructure at 773 K, thus suggesting the observed Xe bubbles after irradiation may shrink and vanish (degassing) upon annealing.
In order to further investigate the formation of such FeCo secondary phase, annealing of a pristine CoCrCuFeNi HCa specimen at 773 K was performed for 2 hours in situ within the TEM without irradiation. The results are shown in Fig. 4 (row e): as noticeable in the elemental maps, only the annealing induces the formation of such a secondary phase. The annealing experiment also revealed strong segregation of Cr within the sub-grain boundaries.
The results of the DPC assessment in both pristine and annealed nanocrystalline CoCrCuFeNi HCA specimens are shown in Fig. 6. The DPC maps in Fig. 6 express the average magnetic momentum of each nanograin in the image plane (represented by the x and y components of the magnetic field, i.e. Bx and By, respectively). In the case of the pristine alloy, the components of the magnetic field are randomly oriented whilst for the annealed case, the presence of FeCo nanoprecipitates led to a strong magnetization and all the FeCo precipitates in the area have their magnetic field aligned in one preferential direction. This finding suggests that the FeCo nanoprecipitates are in fact ferromagnetic with a monodomain innerstructure.
In addition to the DPC analysis, a detailed STEM-EDX quantification of such FeCo nanoprecipitates is presented in Fig. 7(a and b). The precipitates are equiatomic in Fe and Co and highly depleted in all other initial alloying elements of the matrix phase. For such a composition as well as temperature of formation (773 K), the binary Fe–Co phase diagram indicates that this phase is the α′ compound which is characterized by an ordered BCC (B2) structure.71 Using the SAED pattern collected after annealing at 773 K, Fig. 7(e), a radial profile integration was performed to plot the reciprocal interplanar spacings as a function of the diffraction intensity. This plot is shown in Fig. 7(d) and it can be noted that low-intensity superlattice reflections corresponding to the FeCo-phase were positively detected and indexed with data available in the literature.72,73
Fig. 7 FeCo elemental quantification, phase diagram and crystallographic identification. STEM-EDX quantification of the FeCo nanomagnets indicated that their stoichiometry is equiatomic as exhibited in figures (a) and (b). (c) Phase diagram analysis from data-available in literature71 indicate this phase is the α′ equilibrium phase of the binary FeCo system with a BCC (B2) crystal structure. The plot in (d) represents a radial profile integration from the SAED pattern in (e) taken after extended annealing at 773 K. Indexing of the reciprocal spacings using literature data72,73 indicates a positive match for the FeCo-phase (extra-spots in red). Note: the atomic fraction reported in (b) is normalised to the unity. |
These results can be better evaluated with the grain growth kinetic analysis carried out with the application of the Alexander–Was model expressed by eqn (1). Kaoumi et al.33 modified the original Alexander–Was model and concluded that an exponent n value around 2 corresponds to a thermally-assisted grain growth regime whereas exponent values around 3 are characteristic of irradiation-induced grain growth at low temperatures. Analysis in the grain size rate eqn (1) indicates that as a function of fluence, the final grain size value D will be dependent on n: the higher the n value, the smaller the rate of grain growth. The results obtained for nanocrystalline CoCrCuFeNi HCA under heavy ion irradiations in the temperature regime of 293–573 K indicate that the exponent n value is 7.3 and 7.7 for the temperatures of 293 and 573 K, respectively. These values are higher than those reported by Kaoumi et al.33 who estimated n around 3 for heavy ion irradiation (0.5 to 1 MeV of either Ar or Kr) on nanocrystalline pure elements such as Zr, Au, Cu and Pt. This result indicates that in this lower temperature regime, grain growth under irradiation is significantly suppressed in the nanocrystalline CoCrCuFeNi HCA when compared with nanocrystalline pure metals. The same mathematical analysis discussion holds for the non-linear fitting parameter K, related with grain boundary mobility and driving force:33 large values of K were estimated in this work for the temperature regime of 293–573 K, i.e. K ≈ 108–109 whereas K ≈ 103–105 nmn dpa−1 was observed for nanocrystalline metals under irradiation according to Kaoumi et al.33 This leads to the conclusion that the grain boundary mobility within the nanocrystalline CoCrCuFeNi HCA is somehow suppressed under irradiation in the mentioned temperature regime. It is worth emphasizing that these values agree with recent data published by our group using ex situ heavy ion irradiations within the MeV energy range.35
A first explanation for such a suppressed grain growth under irradiation within the regime of 293–573 K is the observation of Cr along the nanograin boundaries as detected via STEM-EDX and shown in Fig. 5. EDX quantification of the pristine alloy as presented in Table 2 shows that the level of Cr within the matrix is around 17.7 ± 2.9 at% whereas after irradiation at 573 K, the level is 20 ± 3.0 at% at the nanograin boundaries: which is a very small difference considering the error margins of the quantification. Thus Cr is observed along the nanograin boundaries with slightly higher content than within the pristine matrix alloy, although such a difference is not large enough to unequivocally conclude there is radiation-induced segregation of Cr. In addition, such a small Cr enrichment may be caused by the 30 min of annealing solely at 573 K prior to irradiation.
Our results in this temperature regime can be understood as a particular feature of the Xe implantation, nanocrystallinity and a particular core-effect of the HCAs. The Xe atom size is relatively large when compared with the alloying elements (Xe atomic radius is 216 pm whereas the average size of the alloy constituents is ≈163 pm), thus its implantation can increase/cause the severe lattice distortion of the nanocrystalline HCA, leading to a small degree of lattice expansion due to atomic size mismatch and subsequently a small expansion of the nanograins. This allows highly mobile Cr atoms to migrate to the grain boundaries as the Cr atom size can be considered “undersized” with respect to the other alloying elements of the matrix, leading to a solute-drag effect. Such an interpretation agrees with recent literature data on ferritic/martensitic steels74 and in the same alloy irradiated by some of the present authors with 3 MeV Ni ions up to 370 dpa.41
The observation of Cr at the nanograin boundaries has major implications for the exhibited high radiation tolerance of the CoCrCuNiFe nanocrystalline HCA in temperatures lower than 573 K. It is believed that such a small enrichment of Cr at intragranular positions will contribute towards mitigation of further grain growth, creating a nanocrystalline material which self-stabilizes under irradiation. The absence of further defects as well as the manifestation of phase transformations for irradiation in this temperature regime may indicate that vacancies have relatively low mobility under irradiation, therefore leading to suppressed grain growth.
STEM-EDX analysis presented in row (c) of Fig. 4 revealed that such grain growth is concomitant with severe Cr depletion and formation of Cr-rich zones (resembling “de-alloying”) and the remaining matrix phase appears to be rich in FeCoNi with some remnants of Cu, but highly depleted in Cr. This Cr depletion from the nanograin boundaries is better visualized considering the Cu elemental map in Fig. 4 (row c) which clearly shows the nanograin boundaries. Interestingly, the Cr depletion from grain boundaries is concomitant with Cr, Fe, Co and Ni segregation (although less noticeable for Co and Ni) at the regions where a higher Xe bubbles areal density is observed, suggesting these elements tend to segregate around the Xe bubbles interfaces. It is worth emphasising that Fe, Co and Ni also segregated at the nanograin boundaries according to the elemental maps in Fig. 4 (row c).
According to He et al.75 on the state-of-the-art of HCAs under irradiation, the mechanisms of RIS on these alloys are under-documented and there is a current lack of experimental results on this topic irrespective of the irradiation type (i.e. ions and neutrons).
In order to understand the Cr depletion and Fe, Co and Ni segregation along the nanograin boundaries in the present nanocrystalline CoCuCrFeNi HCA, we briefly overview RIS. Late in 1970s, Okamoto and Rehn defined RIS as a non-equilibrium thermodynamic process that manifest in binary and ternary alloys under irradiation at homologous temperature within the range of 0.3 ≤ Tm ≤ 0.5 (where Tm is the melting point) resulting in the segregation or depletion of an alloy constituent at point defect sinks.76 This segregation is dependent on the coupling of irradiation-displaced solute atoms with the influx of point defects towards sinks. Such a coupling often occurs on solutes with low self-diffusivities and the excess vacancies generated per ion collisions.77 In this way, solutes with low diffusivities tend to segregate at interfaces whereas solutes with high diffusivities tend to deplete.
Within the nuclear materials community, this interpretation of the RIS phenomenon is known as the Inverse Kirkendall Effect (IKE).78 IKE has been extensively used over the years to explain RIS within the microchemistry of austenitic stainless steels under irradiation.75,79–83 These steels are cast in the ternary system Fe–Cr–Ni which is homologous to the herein studied quinary Co–Cr–Cu–Fe–Ni. In this class of steels, the element Cr has the highest diffusivity as experimentally measured by Rothman et al.84 using radioactive tracers. As reported by these authors, on the ternary system Fe–Cr–Ni, the diffusivity order is DCr < DFe < DNi and the reported ratios between and are 2.5 and 1.8, respectively. Under irradiation, Fe–Cr–Ni steels experience on Cr depletion and Ni enrichment at the grain boundaries. This trend of Cr depletion and Fe, Co and Ni segregation at the nanograin boundaries was observed for the heavy-ion irradiations in this present work for the nanocrystalline CoCrCuFeNi HCA, suggesting that the classical IKE effect operates in this alloy under the studied irradiation conditions.
To better understand the Cr depletion phenomenon is required, thus an extended thermal annealing experiment was performed in the irradiated alloy after the 11 dpa at 773 K irradiation. The post-irradiation and -annealing characterisation (Fig. 4 row d) showed that Cr is re-inserted into the random solid solution which apparently led to the reorganisation of the alloy's original morphology; however the formation of FeCo nanoprecipitates is noted. These FeCo precipitates are depleted of the other alloying elements, indicating that a phase transformation took place. Starting from a pristine (i.e. unirradiated) specimen, extended annealing at 773 K also led to the formation of such FeCo nanoprecipitates. It is also worth emphasising the intra-subgranular Cr content in the annealed specimen at 773 K (Fig. 4 row e) is visually higher than the Cr content in the irradiated plus annealed specimen at 773 K (Fig. 4 row d): while annealing only promotes Cr segregation to the subgrain boundaries, the irradiation plus annealing presents strong Cr depletion at all interfaces, thus following the IKE concepts introduced above. Comparing the annealed and irradiated to the annealed only, the morphology and general aspect of the FeCo nanoprecipitates seems to be complete in the annealed only specimen and not completed in the annealed plus irradiated specimen. This suggests the formation of FeCo nanoprecipitates is somehow favoured upon reincorporation of Cr back into the solid solution.
The observed results within this temperature regime suggest that vacancies have high mobility in this nanocrystalline HCA alloy, despite some of the constitutive core-effects of HCAs such as sluggish-diffusion of defects and high matrix phase stability for the classic Cantor's alloy when exposed to high temperatures.8,12,85,86
Such affirmation above is supported by two major experimental results. Firstly, Xe bubbles observed within this temperature regime were relatively large, with sizes within the range of 20–60 nm. This is of significance as in order for bubbles to grow (without coalescence), a continuous arrival of vacancies (and also Xe interstitials) is required and the final size of an equilibrium bubble is proportional by this vacancy influx until the its internal pressure is balanced with its surface energy (i.e. where p is the internal pressure, γ is the surface energy and r the bubble radius87). Additionally, upon annealing after irradiation at 773 K, Xe bubbles escape through the surfaces of the lamellae which takes place when the bubbles reach the lamellae surface. The second experimental observation that suggests a high mobility of vacancies in this temperature regime is the massive reorganisation of the alloy's local chemistry either under irradiation or annealing. Excess vacancies are required for Cr to segregate out of solid solution under irradiation according to the IKE model. In addition, the formation of FeCoNi- and Cr-rich partitioned zones are dependent on these excess vacancies as solid-state diffusion is required.
Within the wide range of experimental conditions studied, the microstructures of the irradiations with subsequent annealing at 773 K (Fig. 4 row d) and after annealing only (i.e. without irradiation) at 773 K (Fig. 4 row e) are very similar, which confirms that the irradiated alloy can be restored to its annealed state at the temperature regime where vacancies are mobile. This indicates that the alloy in its as-deposited state is found to be in a metastable condition and upon annealing at high temperatures, a new equilibrium state is achieved: the FCC CoCrCuFeNi HCA alloy plus the BCC FeCo nanoprecipitates with the observed microstructure after only irradiation at 773 K being a non-equilibrium state condition. As for better understanding of the grain growth phenomenon under irradiation, further studies are also required to evaluate the interaction between point defects, grain boundary mobility and irradiation temperature, in particular for the case of nanocrystalline HCAs such as the CoCrCuFeNi in this work.88
Although the nanocrystalline HCA herein under investigation may not be suitable for application in harsh environments at high-temperatures, the data in this work indicate that not all HCA can be considered radiation resistant without a detailed study over a wide range of temperatures and large irradiation doses.
Achieving ferromagnetic properties in nanocrystalline materials is a recurrent challenge within the field of nanotechnology. Despite the fact bulk equiatomic FeCo magnetic alloys were firstly synthesized around 1920s,90–92 this present work demonstrated that FeCo nanomagnets can be easily synthesized via thermal annealing at relatively intermediate temperatures (773 K) starting with a nanocrystalline CoCrCuFeNi HCA (as-deposited) and, more important, they remain thermodynamically stable at room temperature (which is a challenge to achieve on nanoscale magnetic materials field93). Another experimental observation is that the FeCo nanomagnets appear not to be stable under heavy ion irradiation, undergoing ballistic-assisted dissolution and mixing;94,95 however, they can be restored upon annealing after irradiation which suggests they are highly stable.
FeCo nanoprecipitates were also observed by Rao et al.96 to form in a FeCoNiMnCu coarse-grained HCA, but only due to thermal annealing. These authors carried out magnetization and Curie temperature measurements and indicated that this FeCo-rich nanophase has potential magnetic properties which fosters new technological applications. In addition, a comprehensive atom probe tomography (APT) study was performed by these authors to characterize the FeCo-phase over a broad range of temperatures, in agreement with the STEM-EDX characterization presented in our work. These works demonstrate that the matrix degradation of HCAs via phase transformations can be used to design materials with unique properties, although HCAs had been previously believed to have a high degree of stability only due to “high-entropy” stabilization of a single phase regardless of their chemical constitution.
Ordered compounds (in their bulk forms, not as nanoprecipitates) like the herein observed FeCo nanomagnets have been reported to exhibit excellent ferromagnetic properties such as high magnetic saturation, high permeability and, more importantly, high coercivity.90 The latter is a measure of “magnetic hardness” which is the ability to retain a magnetic field after the removal of external driving forces,93 which is inversely proportional to the grain size. This suggests that the FeCo nanomagnets are promising materials to be studied within the field of spintronics97 as due to their reduced dimensions at the nanoscale, a competition between the quantum mechanical exchange and magnetostatic energies results in the generation of single giant spins according to Brown's theory of fine-magnetic particles.98 Such an effect has been extensively studied in semiconductors via absorption of single photons which induce the generation of giant spin polarons thousands of times higher than the Bohr's magneton.99
The presence of FeCo nanomagnets as observed in this work could be further explored in the context of micro-nano devices, an emerging new field of research where electromagnetic fields and radiation can be manipulated in solid-state at the nanoscale.100,101 In addition, measurements on coercivity, saturation magnetization and Curie temperature estimation should be carried out following the discoveries reported on this present work regarding the presence of FeCo nanomagnets. A present limitation to perform such magnetization measurements is the thickness of the magnetron-sputtered CoCrCuNiFe nanocrystalline HCA films (around 70 nm) and the size of the FeCo nanomagnets which may generate signals of low intensity, thus impairing the magnetic measurements using conventional magnetometer techniques. A recent paper performed nanoscale measurements on the magnetic properties of FeCo-rich nanomagnets using spin-polarized scanning tunneling microscopy (SP-STM) and their potential for applications in emerging technological areas was fully revealed.102
A comprehensive assessment using in situ TEM ion irradiation and post-irradiation S/TEM analysis was performed and the obtained results allowed the identification of two different regimes of radiation responses pertaining to the mobility of irradiation-induced defects within the alloy microstructure:
• In the first regime of irradiation within the temperature range from 293 to 573 K, no significant alterations were observed to occur within the alloy's initial microstructure and a high degree of radiation tolerance was observed. Grain growth was minor due to the slight enrichment of Cr along the nanograin boundaries which is not high enough in elemental content to indicate that RIS took place. In this temperature regime, neither Xe bubbles nor phase transformations were observed to take place, thus vacancies were considered to have low mobility.
• In the second irradiation temperature range, specifically at 773 K, matrix phase instabilities were detected and characterized using electron-microscopy methods. Irradiation at 773 K led to matrix phase decomposition into a CoCuFeNi-rich phase and regions with high depletion of the element Cr pointing to the occurrence of the classical inverse Kirkendall effect as it happens for austenitic stainless steels under irradiation (Fe–Cr–Ni). The nucleation of large Xe bubbles as well as alterations in the alloy's local chemistry led to the indication that vacancies are mobile in this regime. Annealing after irradiation at 773 K led to the formation of a CoCuCrFeNi matrix and the precipitation of nanoscale FeCo monodomains. The latter microstructure was also reproduced only via annealing the pristine alloy at 773 K, suggesting that the thermodynamic equilibrium state of this quinary system can be composed of FCC CoCuCrFeNi as the matrix phase along with the BCC ordered FeCo nanoprecipitates: indicating that the as-deposited alloy is metastable.
Despite the instabilities observed at intermediate temperatures which may limit the application of this nanocrystalline alloy as a structural material for nuclear reactors, we report a new way to synthesize FeCo nanoprecipitates which exhibit magnetic properties upon DPC assessment within the analytical electron-microscope. These FeCo nanomagnets were also previously characterized to possess excellent magnetic properties to be considered as candidate materials for further investigations within the scope of spintronics, as their reduced dimensions may give rise to unique magneto-transport and magnetic properties given the high-magnetic saturation, high-permeability and high-coercivity often exhibited by bulk FeCo alloys. Such FeCo nanomagnets could also be further studied within the context of the emerging field of micro-nano devices where electromagnetic fields can be manipulated at the nanoscale.
Therefore, the present research work suggests that thermodynamic instabilities in novel high-entropy alloys can actually be beneficial to technological areas where the synthesis of complex materials is a major concern. In addition, the thermodynamic instabilities detected experimentally in this work can support a subsequent in-depth thermodynamic assessment of the quinary CoCuCrFeNi alloy system.
Footnote |
† Electronic supplementary information (ESI) available. See DOI: 10.1039/d1nr04915a |
This journal is © The Royal Society of Chemistry 2021 |