Swelling of uranium by mechanical cavitation

Angerman, C.L.; Caskey, G.R.

doi:10.1016/0022-3115(64)90039-x

Cited by 35 publications

(9 citation statements)

References 8 publications

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“…The growth coefficient for the b axis at 50 K is G b = 21500 [45]; this gives A b = 6.7 × 10 -3 according to Eqn. (7). The MD simulation gives A b = 1.81 × 10 -3 (Fig.…”

Section: Comparison To Experimentsmentioning

confidence: 94%

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Chernatynskiy

Kennedy

et al. 2016

Journal of Nuclear Materials

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“…The growth coefficient for the b axis at 50 K is G b = 21500 [45]; this gives A b = 6.7 × 10 -3 according to Eqn. (7). The MD simulation gives A b = 1.81 × 10 -3 (Fig.…”

Section: Comparison To Experimentsmentioning

confidence: 94%

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Chernatynskiy

Kennedy

et al. 2016

Journal of Nuclear Materials

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“…The fuel alloys have been tailored to promote efficiency and safety, capitalizing on the relatively stable behavior of γ-U in comparison to α-U. The orthorhombic α-phase is defined by anisotropy in radiative swelling and elastic behavior [2], while the body-centered cubic γ-phase has demonstrated predictable and preferred isotropic behavior [3]. In monolithic fuel plates, uranium has been alloyed with varying molybdenum content to promote the γ-phase stability.…”

Section: Introductionmentioning

confidence: 99%

Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

Newell

Park

Mehta

et al. 2017

Journal of Nuclear Materials

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Nanomechanical properties, specifically the reduced modulus and hardness of several intermetallic and solid solution phases are reported to assist the development of the U-10 wt.% Mo (U-10Mo) monolithic fuel system for research and test reactors. Findings from this study and reported values of mechanical properties provide data critical for understanding and predicting the structural behavior of the fuel system during fabrication and irradiation. The phases examined are products of interdiffusion and reaction between (1) the AA6061 cladding and the Zr diffusion barrier, namely (Al,Si) 3 Zr and Al 3 Zr, (2) the U-10Mo fuel and the Zr diffusion barrier, namely UZr 2 , Mo 2 Zr, and α-U, and (3) the U (or U-10Mo) and Mo, namely a mixture gradient of αand γ-phases. The UC inclusions observed within the fuel alloy were also examined. Only phases present in thick or continuous microstructure on cross-sectioned fuel plates and diffusion couples were investigated for reduced modulus and hardness. Concentrationdependence of room-temperature reduced modulus in U solid solution with 0 to 10 wt.% Mo was semi-quantitatively modeled based on mixture of αand γ-phases and solid solutioning within the γ-phase.

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“…The reactor conditions and neutron flux were not provided. Overall, their observations were very similar Around the same time, Angerman and Caskey [48] reported microstructural changes in α-U over the range of 403-823 K and at burnups of 0.05 and 0.77 at%. The reactor conditions and neutron flux were not provided.…”

Section: Irradiation-induced Growth and Swellingmentioning

confidence: 62%

“…Figure 8 summarizes the complex irradiation swelling behaviors as a function of temperature. Around the same time, Angerman and Caskey [48] reported microstructural changes in α-U over the range of 403-823 K and at burnups of 0.05 and 0.77 at%. The reactor conditions and neutron flux were not provided.…”

Section: Irradiation-induced Growth and Swellingmentioning

confidence: 88%

“…The cavities were mostly found in grain boundaries or junctions with angular incisions. Angerman and Caskey [48] reported pronounced variations in microstructure and cavitation (formation of mechanical cavities/voids) with burnup, as shown in Figure 9. At burnups below 0.1 at%, the grain structure of the uranium was easily recognizable regardless of the irradiation temperature, though some grain boundary cracking was observed at high irradiation temperatures.…”

Section: Irradiation-induced Growth and Swellingmentioning

confidence: 96%

See 1 more Smart Citation

A Review of Irradiation Damage and Effects in α-Uranium

2022

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Understanding irradiation damage and effects in α-uranium (α-U) is critical to modeling the behavior of U-based metallic fuels. The aim of this review is to address the renewed interest in U-based metallic fuels by examining the state-of-the-art knowledge associated with the effect of irradiation on the microstructure, dimensional changes, and properties of α-U. We critically review the research progress on irradiation-induced growth and swelling, the enhancement of plastic flow and superplasticity by irradiation, and the effect of irradiation on thermal and electrical properties of α-U. Finally, we outline the research directions that require advancements, specifically the need to carry out fundamental research on several of the less understood mechanisms of irradiation damage and effects in α-U.

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Swelling of uranium by mechanical cavitation

Cited by 35 publications

References 8 publications

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Lattice expansion by intrinsic defects in uranium by molecular dynamics simulation

Mechanical properties examined by nanoindentation for selected phases relevant to the development of monolithic uranium-molybdenum metallic fuels

A Review of Irradiation Damage and Effects in α-Uranium

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