Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy

Huang, Ke; Park, Y.; Keiser, Dennis D.; Sohn, Yong Ho

doi:10.1007/s11669-012-0106-0

Cited by 31 publications

(23 citation statements)

References 20 publications

(23 reference statements)

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“…Likewise, the interface between the Zr and the U-Mo alloy reveals two prominent features as a result of the hot co-rolling and HIP bonding fabrication process. According to the literature [4][5][6]14], these features are likely a uniform UZr 2 phase and globular Mo 2 Zr precipitates. Previous studies have indicated that these intermetallics range from 1.75 µm to 2.84 µm in thickness [4], with the volume fraction of Mo 2 Zr precipitates increasing with decreased annealing temperature [5].…”

Section: Optical Metallographymentioning

confidence: 92%

“…Finally, a Zr diffusion barrier (a lower conductivity material) is used between the U-Mo and aluminum alloy 6061 (AA6061) [3]. Interaction between the Zr and U-Mo fuel alloy during fabrication results in a series of intermetallics (most notably δ-UZr 2 and Mo 2 Zr) that can be further enhanced during irradiation [4][5][6]. Segregation effects resulting from γ -phase destabilization as well as irradiation damage at the fuel-Zr interface (where gross porosity tends to agglomerate in the latter stages of irradiation) can also be detrimental to fuel conductivity during irradiation.…”

Section: Introductionmentioning

confidence: 99%

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Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

et al. 2014

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The uranium-molybdenum (U-Mo) alloy in a monolithic form has been proposed as one fuel design capable of converting some of the world's highest power research reactors from the use of high enriched uranium to low enriched uranium. One aspect of the fuel development and qualification process is to demonstrate appropriate understanding of the thermal-conductivity behavior of the fuel system as a function of temperature and expected irradiation conditions. The purpose of this paper is to verify functionality of equipment installed in hot cells for eventual measurements on irradiated uranium-molybdenum (U-Mo) monolithic fuel specimens, refine procedures to operate the equipment, and validate models to extract the desired thermal properties. The results presented here demonstrate the adequacy of the equipment, procedures, and models that have been developed for this purpose based on measurements conducted on surrogate depleted uranium-molybdenum (DU-Mo) alloy samples containing a Zr diffusion barrier and clad in aluminum alloy 6061 (AA6061). The results are in excellent agreement with thermal property data reported in the literature for similar U-Mo alloys as a function of temperature.

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Section: Optical Metallographymentioning

confidence: 92%

Section: Introductionmentioning

confidence: 99%

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

et al. 2014

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“…Jue et al [22] furthermore reported complex (i.e., distorted and smeared) microstructure near the edge of the fuel within the cladding and none-Zr-coated fuel region. Huang et al [23] examined the diffusion couples between U10Mo alloy and pure Zr, but were unable to document any significant interaction at temperature below 700°C.…”

Section: Introductionmentioning

confidence: 99%

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Park

Eriksson

Keiser

et al. 2015

Materials Characterization

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Microstructural anomalies in the co-rolled-and-HIP'ed U-10 wt.% Mo (U10Mo) metallic fuel plate with Zr diffusion barrier assembly were examined as a function of HIP temperature (from 520 to 580°C) and duration (45, 60, 90, 180 and 345 min) by scanning and transmission electron microscopy. The anomalies observed in this study are carbide/oxide inclusions within the U10Mo fuel alloy, and regions of limited interaction between the U10Mo alloy and Zr barrier, frequently associated with carbide/oxide inclusions. In the U10Mo alloy, the cF8, Fm3m (225) UC phase (a = 4.955 Å) and cF12, Fm3m (225) UO 2 phase (a = 5.467 Å) were observed throughout the U10Mo alloy with an approximate volume percent of 0.5 to 1.8. The volume percent of the UC-UO 2 inclusions within the U10Mo alloy did not change as functions of HIP temperature and time. These inclusion phases, located near the surface of the U10Mo alloy, were frequently observed to impede the development of interdiffusion and reaction between the U10Mo alloy and Zr diffusion barrier. The regions of limited interaction between the U10Mo and Zr barrier decreased with an increase in HIP temperature, however no noticeable trend was observed with an increase in HIP duration at constant temperature of 560°C.

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“…Interactions between the U-Mo and AA6061 take place at high temperature (450~650°C) during fuel plate manufacturing, and at lower temperature in reactor (well below 300°C), however possibly with irradiation-enhancement. 4 To reduce the overall kinetics and complexity of this diffusion interaction, Zr can be used as a diffusion barrier between the U-Mo fuel and AA6061 cladding [19,26,27]. Consequently, however, interdiffusion and reactions can occur between U-Mo and Zr, as well as Zr and AA6061 during the fuel plate fabrication.…”

Section: Introductionmentioning

confidence: 99%

Interdiffusion and reactions between U–Mo and Zr at 650 °C as a function of time

Park

Keiser

Sohn

2015

Journal of Nuclear Materials

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Development of monolithic U-Mo alloy fuel (typically U-10wt.%Mo) for the Reduced Enrichment for Research and Test Reactors (RERTR) program entails a use of Zr diffusion barrier to eliminate the interdiffusion-reactions between the fuel alloy and Al-alloy cladding. The application of Zr barrier to the U-Mo fuel system requires a co-rolling process that utilizes a soaking temperature of 650°C, which represents the highest temperature the fuel system is exposed to during both fuel manufacturing and reactor application. Therefore, in this study, development of phase constituents, microstructure and diffusion kinetics of U-10wt.%Mo and Zr was examined using solid-to-solid diffusion couples annealed at 650°C for 240, 480 and 720 hours. Phase constituents and microstructural development were analyzed by scanning electron microscopy (SEM) and transmission electron microscopy (TEM). Concentration profiles were mapped as diffusion paths on the isothermal ternary phase diagram. Within the diffusion zone, single-phase layers of -Zr and -U were observed along with a discontinuous layer of Mo 2 Zr between the -Zr and -U layers. In the vicinity of Mo 2 Zr phase, islands of -Zr phases were also found. In addition, acicular -Zr and U 6 Zr 3 Mo phases were observed within the -U(Mo) terminal alloy. Growth rate of the interdiffusion-reaction zone was determined to be 1.81 x 10 -15 m 2 /sec at 650°C, however with an assumption of a certain incubation period.

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Interdiffusion Between Zr Diffusion Barrier and U-Mo Alloy

Cited by 31 publications

References 20 publications

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

Development and Validation of Capabilities to Measure Thermal Properties of Layered Monolithic U–Mo Alloy Plate-Type Fuel

Microstructural anomalies in hot-isostatic pressed U–10 wt.% Mo fuel plates with Zr diffusion barrier

Interdiffusion and reactions between U–Mo and Zr at 650 °C as a function of time

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