Beta phase gallium oxide (β-Ga2O3) is emerging as a promising material for space applications due to its unique properties and potential high performance in extreme environments. In this work, we systematically study the impact of β-Ga2O3 Schottky barrier diodes (SBDs) under a high fluence neutron irradiation to explore the degradation mechanism of the devices. After irradiated by neutrons with an average energy of 1–2 MeV and a dose rate of 1.3 × 1012 cm−2 s−1, SBDs with a homoepitaxial layer suffered serious performance degradation. The main manifestation of this degradation was a substantial increase in on-resistance, which rose from 3.9 to 3.5 × 108 mΩ·cm2 under the aforementioned irradiation conditions. The appearance of amorphous/polycrystalline striped lattice damage in the epitaxial layer as well as the presence of deep-level defects caused by oxygen vacancies are factors related to this phenomenon. The simulation revealed that the capture reaction of neutrons and Ga elements is the primary cause of neutron irradiation. This reaction generates high-energy beta- particles (β-particles) resulting in the formation of defects. This paper reveals the degradation mechanism of β-Ga2O3 SBDs under neutron irradiation and provides a possible design roadmap for radiation-resistant β-Ga2O3 power devices. Moreover, a high-temperature oxygen annealing process was implemented, which proved to be in restoring the device performance.

Owing to its ultra-wide bandgap (4.5–4.9 eV), high critical breakdown field (8 MV/cm), large Baliga's figure-of-merit and high thermal stability, β-Ga2O3 has emerged as a promising candidate material for high-efficiency power switching applications.1,2 In recent years, β-Ga2O3 power devices have undergone rapid development with notable progress made in the design and fabrication of high-performance Schottky barrier diodes (SBDs) and PN heterojunction diodes.3–5 With the support of the terminal structure, such as thermally oxidized termination,6 field-plated trench,7 and high-k field plate,8 the performance of the diode is gradually approaching the theoretical limit of β-Ga2O3. Additionally, there have been achievements in the realization of enhancement-mode transistors.9–12 These research findings suggest promising opportunities for the application of β-Ga2O3 devices.

β-Ga2O3 power devices have potential to withstand harsh operating conditions encountered in nuclear and space missions, which makes them a promising candidate for these applications.13,14 In radiation environments, energetic particles, such as neutrons and protons, can induce displacement damage (DD) in the devices, leading to performance degradation.15–17, β-Ga2O3 has been shown to have possible better radiation hardness compared to other semiconductors such as Si and GaN. This is attributed to the higher displacement energies (Ed) of β-Ga2O3 atoms, where Ed (Ga) and Ed (O) are 25 and 28 eV, respectively.18 In contrast, Si has an Ed value of 13 eV,19 and GaN has Ed values of 20 and 10–20 eV for Ga and N atoms, respectively.20 The higher Ed values of β-Ga2O3 result in a greater resistance to vacancy defects and allow it to maintain stable electrical properties even after exposure to high radiation doses. Nonetheless, further studies are needed to fully understand the effects of radiation on β-Ga2O3 devices and to optimize their performance for specific applications. The use of deep level optical spectroscopy (DLOS) and deep level transient spectroscopy (DLTS) enables the determination of the concentration and thermal emission rate of semiconductor deep levels by capacitance characteristics.21,22 Thus, the evolution of defects in β-Ga2O3 has been studied before and after exposure to proton and neutron irradiation using DLOS and DLTS.18,23–26 Furthermore, the researchers demonstrated that β-Ga2O3 transistors and diodes are able to withstand radiation under the high dose of gamma ray, suggesting their potential for use in space missions and other relevant scenarios.27–30 However, the physical source underlying defect formation, defect structure, and microscopic morphology by irradiation remains subjects of ongoing investigation. Therefore, this paper aims to investigate the degradation mechanism of β-Ga2O3 SBDs under neutron irradiation.

In this work, we applied a high dose of neutron irradiation whose schematic and transmission electron microscope (TEM) cross sections are shown in Fig. 1(a). Based on the results of energy dispersive spectroscopy (EDS) tests, the diffusion of Ni did not occur within the error range (±2%). Thus, the phenomenon observed in this paper is not caused by the diffusion of metal. SBDs were produced on 10 μm epitaxial layers utilizing a halide vapor phase epitaxy (HVPE) growth method on (001) β-Ga2O3 bulk substrates (HVPE_SUB) with a doping concentration of 5.5 × 1018 cm−3 by edge-defined film-fed (EFG) purchased from Novel Crystal Technology (Japan). The anode and cathode of the SBDs were formed using Ni/Au (20/100 nm) with a radius of 100 μm and Ti/Au (20/100 nm) metal stacks, respectively, which were deposited on the front and back sides of the sample using electron-beam evaporation. Neutron irradiation experiments were carried out in the JSI research reactor of TRIGA type in Ljubljana.31 The neutrons used for irradiation were derived from a distribution spectrum, which, when normalized based on non-ionization energy loss, corresponds to neutron irradiation with energies ranging from 1 to 2 MeV. The total dose rate applied was 1.3 × 1012 cm−2 s−1, resulting in three total fluence of 8 × 1014 cm−2 (8E14), 1.5 × 1015 cm−2 (1.5E15), and 2.5 × 1015 cm−2 (2.5E15). The SBD subjected to an irradiation dose of 8 × 1014 demonstrates a comparatively smaller performance degradation when compared to the other two doses as shown in Fig. 1(b). Moreover, the distinction in performance degradation between the doses of 1.5E15 and 2.5E15 is already minimal. Nevertheless, the device exhibited complete failure at all three neutron fluence. This phenomenon can be attributed to the complete degradation of the device, indicating that it has reached the maximum level of damage resulting from neutron irradiation. In addition, since the damage inflicted on β-Ga2O3 by the three different irradiation fluences does not exhibit a consistent trend and within the margin of error can be considered indistinguishable, we only show material and device characterization at a dose of 1.5 × 1015 cm−2 in the following text. The displacement damage dose, Ddisp, is considered to account for the displacement damage events in irradiation experiments, which is a measure of imparted energy per unit mass expected from a neutron field. When assuming an equivalent neutron displacement damage cross section ( σ disp) of 92.3 MeV·mb, the Ddisp is calculated to be 2.01 × 1011, 3.77 × 1011, and 6.28 × 1011 MeV/g for three total fluence, respectively. The mean free path for scattering interaction of the neutrons (λs) was determined to be greater than 1 cm for the neutron energy range of 1–2 MeV in β-Ga2O3, and the neutron energy distribution of the incident and outgoing β-Ga2O3 SBDs was basically unchanged in this work using Monte Carlo N-particle transport code (MCNP) software.32 Therefore, if the neutrons are incident from the bottom, their effect on the experimental results would be insignificant.

FIG. 1.

(a) Schematic, TEM cross section of β-Ga2O3 SBDs and the distribution of Ni elements in the same area after irradiation by EDS tests. (b) Forward I–V curves of the SBDs in linear and semi-logarithmic scale of three doses.

FIG. 1.

(a) Schematic, TEM cross section of β-Ga2O3 SBDs and the distribution of Ni elements in the same area after irradiation by EDS tests. (b) Forward I–V curves of the SBDs in linear and semi-logarithmic scale of three doses.

Close modal

The forward current of SBD after irradiation (SBD_AI) has a serious performance degradation compared to that before irradiation (SBD_BI) as shown in Fig. 2(a). After irradiation, the differential specific on-resistance (Ron,sp) of the SBD increased significantly from 3.9 to 3.5 × 108 mΩ·cm2 and the on/off ratio which is defined as I@2 V/I@−2 V decreased from 1011 to 103. On the contrary, as Fig. 2(b) shows, by the H. C. Montgomery method,33 the carrier concentration of the device substrate did not decrease significantly before and after irradiation (HVPE_SUB_BI and HVPE_SUB_AI) owing to the substantial doping of the substrate. From this result, the epitaxial layer has a very serious electrical performance degradation, which can also be verified from the capacitance–voltage (C–V) results as shown in Fig. 2(c). According to the results of C–V measurements, the net doping concentration (ND) of the HVPE epitaxial layer prior to irradiation is approximately 1.67 × 1016 cm−3. In contrast, the SBD_AI exhibits a low capacitance that remains constant across different reverse voltages, suggesting that the epitaxial layer has a very low carrier concentration. Thus, β-Ga2O3 SBDs with HVPE epitaxial layers were completely damaged under this irradiation doses. Both the epitaxial layer and the substrate experience a decrease in the carrier concentration. However, owing to the substantial doping of the substrate, the impact of this reduction may not be readily evident.

FIG. 2.

(a) Forward J–V curves of the SBD_BI and SBD_AI in linear and semi-logarithmic scale. Inset: forward I–V curves of the SBD_AI in the linear scale. (b) Schematic diagram of the test applying the H. C. Montgomery method with 0.5 × 0.5 cm2 HVPE_SUB. (c) Linear-scale of C–V and 1/C2–V characteristics with extracted carrier concentration ND of SBDs. (d) Breakdown characteristics of SBD_BI and SBD_AI in semi-logarithmic.

FIG. 2.

(a) Forward J–V curves of the SBD_BI and SBD_AI in linear and semi-logarithmic scale. Inset: forward I–V curves of the SBD_AI in the linear scale. (b) Schematic diagram of the test applying the H. C. Montgomery method with 0.5 × 0.5 cm2 HVPE_SUB. (c) Linear-scale of C–V and 1/C2–V characteristics with extracted carrier concentration ND of SBDs. (d) Breakdown characteristics of SBD_BI and SBD_AI in semi-logarithmic.

Close modal

In addition, the block and breakdown characteristics are optimized after irradiation, which is mainly reflected in the increase in the breakdown voltage as shown in Fig. 2(d). Although the reverse characteristic does not display any degradation or even indicates an “improvement,” it does not hold any substantial significance when compared to a fully compensated epitaxial layer. Thus, the primary emphasis of this paper is to investigate the underlying physical mechanisms behind device failure caused by neutron irradiation with the aim of offering insight and guidance for future radiation-resistant device design. Some parameters of SBD_BI and SBD_AI are shown in Table I.

TABLE I.

Some electrical parameters of SBD_BI and SBD_AI, including built-in potential (Vbi), Ron,sp, current density at reverse bias voltage 100 V (J@−100 V), on/off ratio, ideality factor, and breakdown voltage (Vbr). The barrier height ( Φ bi _ IV) of SBD_AI is difficult to extract (DE) through the data. The values in bold have obvious changes.

Device V b i (V) R o n , s p (mΩ·cm2) J @ 100 V (nA/cm2) o n / off ratio n Φ b i I V (eV) V b r (V)
SBD_BI  1.00  3.9  97.4  ∼ 1011  1.09  1.11  830 
SBD_AI  0.57  3.5 × 108  22.8  103  1.62  DE  1370 
Device V b i (V) R o n , s p (mΩ·cm2) J @ 100 V (nA/cm2) o n / off ratio n Φ b i I V (eV) V b r (V)
SBD_BI  1.00  3.9  97.4  ∼ 1011  1.09  1.11  830 
SBD_AI  0.57  3.5 × 108  22.8  103  1.62  DE  1370 

Neutron irradiation commonly induces DD within materials. Therefore, we characterized the crystal quality and defects of the epitaxial layer material to explore the degradation mechanism of the devices. As shown in Fig. 3(a) via x-ray diffraction (XRD), the quality of the epitaxial layer crystal has significantly deteriorated after irradiation. This deterioration is reflected in the decrease in the intensity and the increase in the full width at half maximum (FWHM) observed in Fig. 3(b). The XRD intensity of the epitaxial layer significantly decreased after irradiation, indicating a reduction in the crystal coherence length. Furthermore, a previously unobserved diffraction peak at 2θ = 37.99° emerged in the XRD spectrum.34 The analysis suggests that the irradiation of the epitaxial layer results in the formation of polycrystalline or amorphous regions. This is consistent with the observed increase in the FWHM of the x-ray rocking curve peaks from the (002) plane of the (001) crystallographic orientation as shown in Fig. 3(b), which indicates a significant decrease in the crystallinity of the material. On the contrary, despite the severe degradation of crystal quality in the epitaxial layer, the substrate retains its excellent single crystal orientation, as depicted in Figs. 3(c) and 3(d). After irradiation, the substrate continues to exhibit a single crystal orientation (001), and there is no substantial increase in FWHM, confirming its retention as a well-organized single crystal material. This observation highlights the critical distinction between the substrate and epitaxy in terms of their resistance to neutron irradiation, primarily stemming from the disparity in crystal quality. HVPE epitaxy is more susceptible to the degradation of crystal quality, whereas the substrate maintains its good single crystal characteristics even after irradiation.

FIG. 3.

XRD patterns (a) and (002) peak rocking curves of (001) Ga2O3 HVPE layers (b) before (HVPE_BI) and after (HVPE_AI) irradiation. XRD patterns (c) and (002) peak rocking curves of (001) Ga2O3 HVPE_SUB_BI and HVPE_SUB_AI (d).

FIG. 3.

XRD patterns (a) and (002) peak rocking curves of (001) Ga2O3 HVPE layers (b) before (HVPE_BI) and after (HVPE_AI) irradiation. XRD patterns (c) and (002) peak rocking curves of (001) Ga2O3 HVPE_SUB_BI and HVPE_SUB_AI (d).

Close modal

In order to more intuitively observe the effect of neutron irradiation on the interface and interior of the device, close-up high-resolution transmission electron microscopy (HRTEM) images, together with their corresponding fast Fourier transform (FFT) patterns, were used to analyze typical regions of the epitaxial layer (labeled by dashed boxes in the HRTEM images) as shown in Fig. 4. The analysis revealed the appearance of darker, streaky areas within the crystal, as shown in Fig. 4(b), which indicates an increased disorder of atomic arrangement. The analysis of the single crystal diffraction (SCD) spectrum of the epitaxial layer following irradiation indicated a higher level of background noise, suggesting an increase in the amorphous components of the material. This finding is consistent with the conclusion drawn from the rocking curves analysis. Additionally, the SCD revealed the appearance of a polycrystalline diffraction ring after irradiation, which is in line with the emergence of observed peaks in the XRD results. These observations provide further evidence for the transformation of the material from a single crystal to a polycrystalline structure due to the irradiation.

FIG. 4.

High-resolution TEM test results and its SCD patterns calculated by FFT of SBD_BI (a) and SBD_AI (b). (c) EDS results were tested following the direction of the red arrow, indicating that stripes in TEM results are related to different Ga/O atomic ratios caused by neutron radiation. (d) TEM images of HVPE_SUB_AI.

FIG. 4.

High-resolution TEM test results and its SCD patterns calculated by FFT of SBD_BI (a) and SBD_AI (b). (c) EDS results were tested following the direction of the red arrow, indicating that stripes in TEM results are related to different Ga/O atomic ratios caused by neutron radiation. (d) TEM images of HVPE_SUB_AI.

Close modal

In order to clarify the cause of these darker streaky areas which is not found in HVPE_BI, we conducted an EDS test as shown in Fig. 4(c). The perpendicular direction to these streaks exhibits a significant variation in the ratio of Ga and O atoms, but the characteristic did not appear in the EDS results for the substrate. Therefore, under the irradiation of high fluence neutrons, the HVPE epitaxial layer would appear striped lattice damage along the injection direction of neutrons, and the width of these stripe shadows is about 2.4 nm. On the contrary, the TEM result of the substrate shows that the atoms are arranged orderly after irradiation as depicted in Fig. 4(d), which illustrates that the substrate exhibits better radiation tolerance in terms of crystal quality.

In order to find the cause of these changing atomic ratio, the x-ray photoelectron spectroscopy (XPS) measurement was carried out, and peak fitting of the Ga3d and O1s core levels was analyzed as shown in Figs. 5(a)–5(f). The standard binding energy of 284.8 eV was chosen for the C1s peak as the reference point.35 The Ga3d peak located at 19.76 eV, corresponding to the peaks due to the Ga–O bonding core level and Ga elements mainly exist in the form of Ga3+. The remaining peaks located at 19.36 eV exist in the form of Ga2+. Similarly, the O1s core levels were divided into two peaks at positions 530.54 and 531.86 eV, representing OI and OII, respectively. Through the result of XPS, the proportion of Ga2+ increases from 0.43 to 0.69, and the ratio of Ga/O increases from 0.7 to 0.8, which means that the proportion of the GaO chemical state increases most likely due to the creation of oxygen vacancies. Following irradiation of both the substrate and HVPE epitaxy, there is an observed increase in the OII/(OI + OII) ratio. This increase signifies a rise in oxygen vacancies within the material. Additionally, these oxygen vacancies may act as deep-level defect to compensate carriers, resulting in a decrease in the carrier concentration. Figures 5(e) and 5(f) present the XPS results obtained from both the irradiated and unirradiated substrates of the HVPE layer. The observed outcomes exhibit a resemblance to those observed in the HVPE epitaxy. Specifically, the proportion of OII was found to increase after irradiation, indicating a notable rise in the content of oxygen vacancies, which verifies the reason for the similar decrease in the carrier concentration of substrate and epitaxial. Furthermore, the conclusions derived from the XPS test indicate no discernible difference between HVPE epitaxy and the substrate regarding the influence of chemical composition. Therefore, the radiation tolerance of the substrate is only manifested in the structural characteristics but not from the electrical one.

FIG. 5.

The chemically bonded Ga3d (a) and (b) and O1s XPS peaks (c) and (d) of HVPE_BI and HVPE_AI. The ratio of atoms before and after irradiation was obtained by (a)–(d). (e) and (f) The O1s XPS peaks and (c) and (d) of HVPE_SUB_BI and HVPE_SUB_AI.

FIG. 5.

The chemically bonded Ga3d (a) and (b) and O1s XPS peaks (c) and (d) of HVPE_BI and HVPE_AI. The ratio of atoms before and after irradiation was obtained by (a)–(d). (e) and (f) The O1s XPS peaks and (c) and (d) of HVPE_SUB_BI and HVPE_SUB_AI.

Close modal
We conducted nuclear reaction simulations of neutron and Ga2O3 to elucidate the reaction mechanism. Due to the presence of two isotopes of natural Ga, Ga-69, and Ga-71, we calculated the macroscopic reaction cross section (MACS) for these isotopes as well as for O-16 in the neutron nuclear reactions, as depicted in Figs. 6(a)–6(c). For both Ga-69 and Ga-71, the MACS for the neutron capture reaction (n, γ) is significantly higher (by two orders of magnitude) than that for other inelastic reactions, such as (n, α) and (n, p), which produce an α particle and a proton, respectively. We also conducted a neutron irradiation simulation for O-16 and found that, except for the (n, γ) reaction, the MACS values for other reactions can be negligible. Figure 6(c) demonstrates the MACS values for the (n, γ) reaction of β-Ga2O3 and suggests that the reaction of Ga atoms is more favorable than that of O atoms. Additionally, the O-17 produced by the (n, γ) reaction of O-16 is a stable nuclide, and the associated energy deposition is minimal; therefore, this reaction can be disregarded. Ga-70 and Ga-72 produced by the reaction of Ga-69 and Ga-71 (n, γ) are unstable nuclides, which can spontaneously decay into Ge-70 and Ge-72. The reaction formula is as follows:
Ga 69 n , γ Ga 70 Ge 70 + β ( T 1 / 2 = 21 min , E = 1.656 MeV ) ,
Ga 71 n , γ Ga 72 Ge 72 + β ( T 1 / 2 = 14.1 h , E = 3.999 MeV ) ,
where T 1 / 2 represents the half-life and E represents the energy of β particle. The reaction rates of Ga-69 and Ga-71 are 6.37 × 108 and 1.95 × 108 cm−3 s−1, respectively. An irradiation time of 1150 s results in the production of Ga-70 and Ga-72, which have a total concentration of 7.35 × 1011 and 2.25 × 1011 cm−3, respectively. The high-energy β particles produced from the decay of Ga-69 and Ga-71 can interact with materials to produce defects. Using the MCNP method, the deposition energy of the generated β particles in the epitaxial layer can be simulated, and it will be estimated that about 1016 cm−3 oxygen vacancies are generated. Additionally, we performed simulations to evaluate the MACS of other doping elements (Sn, Si) and residual elements (Cl) with neutrons. The simulation results indicated significantly lower MACS compared to Ga elements. Their impact on neutron-induced damage in the material can be considered negligible. Therefore, other elements do not influence the neutron damage in β-Ga2O3. Based on the simulation results, the contribution of traditional doping elements to neutron radiation damage is minimal. It is feasible to mitigate the influence of radiation on the crystal structure through the doping of elements with substantial neutron capture cross sections, such as 10B or 6Li, as internal reaction sources within the material. According to the above tests and analysis, the band diagram and schematic diagram of the interaction between neutrons and β-Ga2O3 are shown in Figs. 6(d) and 6(e), respectively.
FIG. 6.

MACS for three nuclear reactions of Ga-69 (a) and Ga-71 (b). (c) The MACS for (n,γ) reactions of three elements. (d) and (e) the band diagram and schematic diagram of the interaction between neutrons and β-Ga2O3.

FIG. 6.

MACS for three nuclear reactions of Ga-69 (a) and Ga-71 (b). (c) The MACS for (n,γ) reactions of three elements. (d) and (e) the band diagram and schematic diagram of the interaction between neutrons and β-Ga2O3.

Close modal

Based on the analysis, the degradation of device performance is primarily attributed to the deterioration of crystal quality and the generation of oxygen vacancies. To address this issue, we conducted an annealing process on the device, subjecting it to a temperature of 300 °C for a duration of 30 min within an oxygen atmosphere.

From Fig. 7(a), the forward characteristics of the irradiated SBD exhibit noticeable restoration after annealing (SBD_AI_AA). Figure 7(b) reveals a decrease in the proportion of OII, suggesting a significant reduction in oxygen vacancies. Moreover, the quality of the epitaxial layer after annealing has been significantly improved: the intensity of the peaks has been greatly increased and the peak position corresponding to (001) has also appeared which meant that the amorphous regions are recovered to the ordered crystal structure. However, the additional crystal orientation peak cannot be eliminated after annealing as shown in Fig. 7(c).

FIG. 7.

(a) Forward characteristics of the device after annealing. (b) The O1s XPS peaks of HVPE after annealing (HVPE_AI_AA). (c) XRD patterns of HVPE_AI_AA.

FIG. 7.

(a) Forward characteristics of the device after annealing. (b) The O1s XPS peaks of HVPE after annealing (HVPE_AI_AA). (c) XRD patterns of HVPE_AI_AA.

Close modal

In summary, we carried out the neutron irradiation experiments on β-Ga2O3 SBDs at a dose rate of 1.3 × 1012 cm−2 s−1. From the test results of I–V and C–V, the Ron,sp of the device increases due to the drastic reduction in the carrier concentration of the epitaxial layer. By utilizing a combination of characterization techniques such as XRD, TEM, EDS, and XPS, we can infer the damage mechanisms induced by neutron irradiation in β-Ga2O3 devices. Upon exposure to a high flux of neutrons, the HVPE layer experiences displacement of oxygen atoms from their original positions by nuclear interactions, leading to the formation of a substantial number of oxygen vacancies. These vacancies contribute to the formation of deep-level defects that act as compensating centers for carriers in the material. Additionally, the β-Ga2O3 lattice undergoes severe disruption due to the bombardment of a large number of neutrons, resulting in displacement damages that take the form of striped lattice damage oriented along the direction of incident neutrons once the system has reached thermal equilibrium. These amorphous/polycrystalline regions will lead to a decrease in the carrier mobility, combined with a decrease in the carrier concentration, which eventually leads to a severe degradation of device performance. Power devices often necessitate low carrier concentrations to achieve higher breakdown voltages. However, lower carrier concentrations lead to a more pronounced carrier removal effect caused by neutron irradiation. Addressing this challenge requires a careful balance between the desired carrier concentration for breakdown voltage requirements and the need to mitigate the detrimental effects of neutron radiation. Approaches, such as enhanced crystal quality, reduce the proportion of Ga elements, and doping of elements with substantial neutron capture cross sections, such as 10B or 6Li, may offer potential solutions to achieve a more favorable compromise between these conflicting requirements in power device applications.

This work was supported by the Fundamental Research Plan under Grant No. JCKY2020110B010, the National Natural Science Foundation of China under Grant Nos. 61925110, 62234007, U20A20207, 62004184, and 62004186, the Key-Area Research and Development Program of Guangdong Province under Grant No. 2020B010174002, the University of Science and Technology of China (USTC) under Grant Nos. YD2100002009 and YD2100002010, the Collaborative Innovation Program of Hefei Science Center, Chinese Academy of Sciences (No. 2022HSC-CIP024), and the Opening Project of and the Key Laboratory of Nanodevices and Applications in Suzhou Institute of Nano-Tech and Nano-Bionics of CAS. This work was partially carried out at the Center for Micro and Nanoscale Research and Fabrication of USTC.

The authors have no conflicts to disclose.

Jinyang Liu: Conceptualization (lead); Data curation (lead); Formal analysis (lead); Investigation (lead); Writing – original draft (lead). Yuncheng Han: Methodology (equal); Writing – review & editing (equal). Xiaohu Hou: Writing – review & editing (equal). Shibing Long: Funding acquisition (equal); Supervision (equal); Writing – review & editing (equal). Zhao Han: Conceptualization (equal); Data curation (equal); Formal analysis (equal); Investigation (equal); Writing – original draft (equal); Writing – review & editing (equal). Lei Ren: Formal analysis (equal). Xiao Yang: Methodology (equal); Writing – review & editing (equal). Guangwei Xu: Formal analysis (equal); Funding acquisition (equal); Supervision (equal); Writing – review & editing (equal). Weibing Hao: Methodology (equal). Xiaolong Zhao: Funding acquisition (equal); Supervision (equal); Writing – review & editing (equal). Shu Yang: Methodology (equal). Di Lu: Writing – review & editing (equal).

The data that support the findings of this study are available within the article.

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