Abstract
U-Mo alloys are being developed as low-enrichment uranium fuels under the Reduced Enrichment for Research and Test Reactor (RERTR) program. Significant reactions have been observed between U-Mo fuels and Al or Al alloy matrix. Refractory metal Zr has been proposed as barrier material to reduce the interactions. In order to investigate the compatibility and barrier effects between U-Mo alloy and Zr, solid-to-solid U-10wt.%Mo versus Zr diffusion couples were assembled and annealed at 600, 700, 800, 900, and 1000 °C for various times. The microstructures and concentration profiles due to interdiffusion and reactions were examined via scanning electron microscopy and electron probe microanalysis, respectively. Intermetallic phase Mo2Zr was found at the interface, and its population increased when annealing temperature decreased. Diffusion paths were also plotted on the U-Mo-Zr ternary phase diagrams with good consistency. The growth rate of interdiffusion zone between U-10wt.%Mo and Zr was also calculated under the assumption of parabolic diffusion and was determined to be about 103 times lower than the growth rate of diffusional interaction layer found in diffusion couples U-10wt.%Mo versus Al or Al-Si alloy. Other desirable physical properties of Zr as barrier material, such as neutron adsorption rate, melting point, and thermal conductivity, are presented as supplementary information to demonstrate the great potential of Zr as the diffusion barrier for U-Mo fuel systems in RERTR.
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Introduction
Uranium-molybdenum (U-Mo) dispersion and monolithic fuels in aluminum (Al) alloys are being developed as a low-enrichment metallic fuel system under the Reduced Enrichment for Research and Test Reactor (RERTR) program.[1-3] Metallurgical interactions occur between the U-Mo fuels and Al alloy matrix during processing and irradiation due to interdiffusion.[4-6] Efforts[7-15] have been made to document complex interactions and deleterious effects such as thinning of the cladding layer, formation of phases with poor irradiation behavior and relative low melting point, and thermal cracks.
Refractory metal Zr has been proposed as barrier layer between the U-Mo fuel and Al alloy matrix to reduce the interactions, since the diffusion of U in Zr is slow,[16-18] and the fabrication of Zr barrier is compatible with the current hot-rolling techniques used by Idaho National Laboratory (INL).[6] Furthermore, interaction products that form between U-Mo fuel and Zr appear to be stable during irradiation.[19] In an as-processed U-10wt.%Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier,[6] multiple phases including αU, Mo2Zr, Zr solid solution, γUZr, and UZr2 were observed at the interface of U-Mo with Zr.
This study systematically investigated the interdiffusion and reaction between U-Mo alloy with Zr, without the influence of multiple and complex hot-rolling process on the interfacial microstructure and phase constituents. Solid-to-solid isothermal diffusion method was used from 600 to 1000 °C. The microstructure and concentration profiles of interdiffusion zone were examined by scanning electron microscopy (SEM) and electron probe microanalysis (EPMA), respectively. Diffusion paths at each temperature were determined and superimposed on the isothermal U-Mo-Zr ternary phase diagrams. The growth rate of interdiffusion zone was also calculated and compared to those of U-Mo versus Al and U-Mo versus Al-Si diffusion couples reported in the literature.[9,20] Other desirable physical properties of Zr as barrier material are also presented.
Experimental Procedure
All metallographical preparation and assembly of diffusion couples were carried out under an argon (Ar) atmosphere inside a glove box to minimize oxidation of the U-Mo alloy and Zr. U-Mo rods were cast using high-purity depleted uranium (DU) and Mo via arc melting. They were melted three times to ensure homogeneity and then drop-cast to form rods with 12.7 mm diameter. Zirconium rods of 99.99% purity (12.7 mm diameter) were acquired from a commercial source (Alpha-Aesar). The homogeneity in composition, phase constituents, and microstructure of the U-Mo and Zr were examined by x-ray diffraction (XRD; Rigaku DMAX-B) and scanning electron microscopy (SEM; Hitachi 3500N) equipped with x-ray energy dispersive spectroscopy (XEDS).
Both the U-Mo alloy and Zr rods were sectioned into 3 mm thick disks, and the surfaces were metallographically polished down to 1 μm using diamond paste. The prepared surfaces were then placed in contact with each other and held together by two clamping disks with stainless steel rods to form a jig. The jig assembly was wrapped in Ta foil, encapsulated in a quartz capsule, and sealed under an Ar atmosphere after repeated vacuum (10−6 Pa) and H2 purge. The couples were annealed using a Lindberg/Blue three-zone tube furnace at the temperatures listed in Table 1. After annealing, the diffusion couples were quenched by breaking the quartz capsule in cold water. Each diffusion couple was then mounted in epoxy, cross-sectioned, and polished using 1 μm diamond paste for microstructural examination and compositional analysis.
For each diffusion couple, SEM was performed to examine the interdiffusion microstructure. Electron probe microanalysis (JEOL Superprobe 733) was used to obtain the concentration profiles of U, Mo, and Zr from each couple using a point-to-point scan with a 5-10 μm step size and an accelerating voltage of 20 keV. The pure metals, DU, Zr, and Mo were used as standards. The intensities of the U-Mα, Zr-Lα, and Mo-Lα x-rays were converted to compositions via ZAF correction.
Results and Discussions
Composition of U-Mo Alloy
The composition of U-Mo alloy was examined by EPMA at 10 random locations. Its average value and standard deviation were determined as reported in Table 2. The averaged composition, 20.91 at.% Mo is very close to the target composition of U-10wt.%Mo fuel, which is 21.61 at.% Mo. The standard deviation of the 10 measured points was 0.15 at.%.
Microstructure, Concentration Profiles, and Diffusion Paths
Backscattered electron (BSE) micrographs and concentration profiles from the U-Mo versus Zr diffusion couples annealed at 1000, 900, 800, and 700 °C are presented in Fig. 1 to 4. Figure 5 shows the interfacial microstructure developed at 600 °C where the couple had a negligible interaction. The large dark precipitates near the interface in Fig. 1 to 4 were identified as Mo2Zr using semiquantitative composition analysis by XEDS and the Mo-Zr equilibrium binary phase diagram presented in Fig. 6.[21] When the diffusion anneal temperature decreased from 1000 to 700 °C, the population of the Mo2Zr precipitates increased (i.e., an increase in volume fraction of Mo2Zr). The U-Mo versus Zr ternary diffusion couples examined in this study have the extra degree of freedom based on Gibbs phase rule that allows the development of two-phase layer that includes Mo2Zr phase. Small dark precipitates present throughout the U-Mo alloy are identified as Zr-rich phase, which is composed of >95 at.% Zr and a few at.% of U and Mo. This tiny Zr-rich precipitate should be the αZr, formed during quenching. The U-Zr solid solution eutectoidally decomposed into αZr and Mo2Zr upon cooling according to the U-Zr phase diagram shown in Fig. 7.[21] Unfortunately, the αZr precipitates are too small in size, and the eutectoid structure cannot be observed clearly.
Concentration profiles determined by EPMA show an uphill diffusion of U on the U-Mo side. Scatter in concentration profiles is observed near the interface because of the Mo2Zr precipitates. When diffusion anneal temperature decreased to 600 °C, U-Mo and Zr diffusion couple exhibited a negligible interaction despite the 960 h of diffusion anneal. A very small intermediate phase with thickness of about 1-2 μm was observed discretely at the interface as seen in Fig. 5. The composition of these intermediate phases has not been determined accurately since the size is too small.
There is an allotropic transformation between αZr and βZr at 863 °C according to U-Zr phase diagram shown in Fig. 7.[21] Therefore, both αZr and βZr exist on the Zr side at 800 and 700 °C as shown in Fig. 3 and 4, while only βZr exists at 1000 and 900 °C as shown in Fig. 1 and 2. A marker plane was clearly observed in diffusion couple annealed at 1000 °C as marked in Fig. 1. However, unfortunately, markers could not be identified in other diffusion couples.
U-Mo-Zr ternary phase diagrams have been determined by Ivanov and Bagrov for isothermal temperature of 500, 575, 600, 625, 650, 675, 700, 750, and 1000 °C.[22,23] The concentration profiles of diffusion couples were plotted as diffusion paths on U-Mo-Zr ternary phase diagrams shown in Fig. 8. Since there is no available ternary phase diagram at 900 and 800 °C, the diffusion paths are presented on the isotherms at 1000 and 750 °C, respectively. Solid circles fitted with solid lines in Fig. 8 present the composition measured by EPMA in single-phase regions. The experimental data within the two-phase region with Mo2Zr precipitates had scatters in composition. Therefore, diffusion path in two-phase region is estimated based on average composition by considering the composition and volume fraction of U-Zr solid solution and precipitates, which is shown as dot line in Fig. 8. In general, the diffusion paths constructed based on EMPA measurement were consistent with the ternary phase diagrams determined by Ivanov and Bagrov.[22,23]
Based on the shape of the diffusion paths and concentration profiles, it is clear that Zr diffuses slowly on the U-Mo alloy side, and Mo is the slow-moving specie on the Zr side. On the U-Mo alloy side, gradients of concentration for Mo and U develop even without a significant diffusional penetration of Zr as shown in Fig. 1 to 4. This is also reflected on the diffusion paths in Fig. 8 wherein the diffusion paths take off toward the pure U corner. While the Mo moves down the concentration gradient, U moves up toward higher U concentration. This result suggests that Zr is an excellent diffusion barrier to retain the high U-density in the U-Mo fuel. With an increase in Zr concentration, diffusion path enters the two-phase (Mo2Zr and γ-U) region. This is consistent with the observation that Mo2Zr precipitates in γ-matrix exist at the interface. The U-Mo-Zr isotherms in Fig. 8 clearly show that a decrease in the temperature from 1000 to 700 °C reduces the U-Zr solid-solution phase field and expands the two-phase (Mo2Zr and γU) field. Correspondingly, the volume fraction of Mo2Zr increased as shown in Fig. 1 to 4.
Toward the Zr end, diffusion path passes through the U-Zr solid solution and ends at pure βZr at higher temperatures of 1000 and 900 °C, as presented in Fig. 8(a) and (b). At 800 and 700 °C, the diffusion path goes through U-Zr solid solution and jumps into αZr with negligible solubility for either U or Mo as presented in Fig. 8(c) and (d). The diffusion paths within the βZr, for example at 1000 and 900 °C, take off from pure Zr toward the U-corner of the isotherm and suggest that Mo is the slow-moving specie in the βZr solid solution. Presence of Mo plays a significant role on the diffusion path and solubility of Zr in U-Zr solid solution, especially at 700 °C. Based on the U-Zr binary phase diagram shown in Fig. 7, the solubility range of Zr in U-Zr solid at 700 °C should be 50-87 at.%. However, the addition of Mo changes the shape of diffusion paths dramatically and alters the diffusion paths to pass just a small U-Zr solid-solution region as shown in Fig. 8(d). This causes the solubility range of Zr in the U-Zr solid solution to be much smaller, which is 85-90 at.%.
Growth Rate of Interdiffusion Zone
For Zr to be an effective diffusion barrier between U-Mo fuel and Al matrix, the overall magnitude of diffusional interaction must be small. Figure 5 shows that negligible interdiffusion was observed even after 960 h of isothermal anneal at 600 °C. To compare and contrast the interdiffusion behavior of diffusion couples U-Mo versus Zr to U-Mo versus Al (or Al-Si alloy), parabolic growth rate, K, of interdiffusion zone was calculated at 1000, 900, and 800 °C. Thickness of interdiffusion zone (IZ) is simply defined as the distance between U-10wt.%Mo and pure Zr where concentration gradient becomes negligible (terminal ends where ∂C/∂x = 0). Growth rates of interdiffusion zone were calculated by assuming K = (∆x)2/2t, where, ∆x is the thickness of IZ, and they are reported in Table 3 for 1000, 900, and 800 °C.
Figure 9 shows that the temperature dependence of the IZ growth rate, K, obeys the Arrhenius relation in the temperature range from 800 to 1000 °C very well. The pre-exponential factor, K o, and activation energy, Q K, of the growth rate were determined and are also reported in Table 3. Growth rates at 700, 600, and 500 °C were then calculated following simple Arrhenius extrapolation as reported in Table 3 and presented in Fig. 9. Table 4 lists the growth rate determined from diffusion couples, U-Mo versus Al and U-Mo versus Al-Si, examined by Perez et al.[9,20] The growth rate was calculated from the thickness of the complex intermetallic layer. Tables 3 and 4 demonstrate that the growth rates of interdiffusion zone between U-10wt.%Mo and Zr is 2-3 orders of magnitude slower than those between U-10wt.%Mo and Al or Al-Si alloys.
Other Desirable Barrier Properties of Zr
The ideal barrier materials for metallic fuel system require:
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Interdiffusion or reactions between barriers and metallic fuels should be slow.
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No or insignificant amount of intermetallic phases should form for better structural integrity. Thermal expansion coefficients and other thermomechanical properties of intermetallic phases may vary significantly. Solid solution is preferred because relevant properties would vary gradually with composition.
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Intermetallic phases, if formed due to interdiffusion and reaction, should be stable under irradiation.
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Melting point should be high.
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Neutron adsorption rate should be low.
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Thermal conductivity should be high.
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Corrosion resistant should be good.
Results from this study demonstrate that diffusional interaction between U-Mo and Zr is slow compared to U-Mo and Al or Al-Si alloys. For the temperature range investigated in this study, only one intermetallic phase Mo2Zr exists as precipitates near the interface. However, at the lower temperature, other intermetallic or solid-solution phases may form according to the U-Mo-Zr ternary phase diagram,[23] such as, UZr2, U4Zr5Mo, U6Zr3Mo, and U2Mo. In Perez’s study,[6] multiple phases including αU, Mo2Zr, U-Zr solid solution, and UZr2 were observed at the interface between U-Mo with Zr in the hot-rolled and annealed U-Mo fuel with Zr as barrier. Therefore, a further investigation of phase equilibrium and diffusional interaction at lower temperature would be required. However, Robinson[19] has reported that the interaction products containing Zr appear to be stable during irradiation.
As a refractory metal, Zr has a very high melting temperature of 1855 °C, and high thermal conductivity of 22.6 W/m·K.[21] The neutron absorption rate of Zr is fairly low. The cross section for 2200 m/s neutrons of Zr is 0.185 barn, which is one of the lowest among naturally occurring metals.[24] Moreover, Zr is highly resistant to corrosion by alkalis, acids, salt water, and other agents.[25] Diffusional interaction between Zr and Al has been studied by Kidson et al.[26] and Laik et al.[27] However, there is discrepancy on the formation and growth rates of intermetallic phases between the two studies. Further investigation into this discrepancy needs to be conducted.
Summary
Diffusional interaction between U-10wt.%Mo alloy and Zr has been systematically studied in the temperature range of 600 to 1000 °C. Mo2Zr has been found at the interface, and its population increased with a decrease in the temperature of diffusion anneal. The diffusion paths were plotted on U-Mo-Zr ternary isotherms and examined with respect to ternary diffusional interactions. The growth rates of interdiffusion zone between U-10wt.%Mo and Zr were found to be about 103 times slower than those between U-10wt.%Mo and Al or Al-Si alloys. Other desirable factors of Zr working as barrier material were also presented.
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Acknowledgments
This work was supported by the U.S. Department of Energy, Office of Nuclear Materials Threat Reduction (NA-212), National Nuclear Security Administration, under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution or to allow others to do so, for U.S. Government purposes.
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Huang, K., Park, Y., Keiser, D.D. et al. Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy. J. Phase Equilib. Diffus. 33, 443–449 (2012). https://doi.org/10.1007/s11669-012-0106-0
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DOI: https://doi.org/10.1007/s11669-012-0106-0