Growth kinetics and microstructural evolution during hot isostatic pressing of U-10wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier

Park, Y.; Yoo, Jang-Yong; Huang, Ke; Keiser, Dennis D.; Jue, Jan‐Fong; Rabin, B. H.; Moore, George A.; Sohn, Yong Ho

doi:10.1016/j.jnucmat.2014.01.018

Cited by 29 publications

(39 citation statements)

References 14 publications

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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%

“…A thin interaction layer between the AA6061 clad and Zr diffusion barrier is observed as a result of the HIP bonding process. This thin layer has been reported to consist of multiple intermetallic layers, e.g., AlSi 4 Zr 5 , (Al, Si) 3 Zr, (Al, Si)Zr 3 , and (Al, Si) 2 Zr, from the Zr to the AA6061 clad [4,6]. These layers are too thin to resolve utilizing optical microscopy in the present work, but have previously been reported to range from 0.28 µm to 2.80 µm [4].…”

Section: Optical Metallographymentioning

confidence: 99%

“…This thin layer has been reported to consist of multiple intermetallic layers, e.g., AlSi 4 Zr 5 , (Al, Si) 3 Zr, (Al, Si)Zr 3 , and (Al, Si) 2 Zr, from the Zr to the AA6061 clad [4,6]. These layers are too thin to resolve utilizing optical microscopy in the present work, but have previously been reported to range from 0.28 µm to 2.80 µm [4]. 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.…”

Section: Optical Metallographymentioning

confidence: 99%

“…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: Optical Metallographymentioning

confidence: 99%

Section: Optical Metallographymentioning

confidence: 99%

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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“…Previous investigations have reported microstructural development in monolithic fuel that consists of U10Mo fuel alloy, Zr diffusion barrier and AA6061 cladding [16,21]. The fuel system is fabricated by sequential process of co-rolling (~650°C) and hot-isostatic press (~520 to 580°C) as schematically illustrated in Fig.…”

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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Microstructural Evolution of the Interdiffusion Zone between U-9 Wt Pct Mo Fuel Alloy and Zr-1 Wt Pct Nb Cladding Alloy Upon Annealing

Neogy

Laik

Saify

et al. 2017

Metall Mater Trans A

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Growth kinetics and microstructural evolution during hot isostatic pressing of U-10wt.% Mo monolithic fuel plate in AA6061 cladding with Zr diffusion barrier

Cited by 29 publications

References 14 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

Microstructural Evolution of the Interdiffusion Zone between U-9 Wt Pct Mo Fuel Alloy and Zr-1 Wt Pct Nb Cladding Alloy Upon Annealing

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