Discontinuous Precipitation in U-10 wt.%Mo Alloy: Reaction Kinetics, Effect of Prior γ-UMo Microstructure, the Role of Grain-Boundary Misorientation, and the Effect of Ternary Alloying Addition

Jana, Saumyadeep; Overman, Nicole; Devaraj, Arun; Sweet, Lucas E.; Lavender, Curt A.; Joshi, Vineet V.

doi:10.1007/s11837-019-03588-4

Cited by 5 publications

(1 citation statement)

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“…The as-received U-7 wt.% Mo sample showed the presence of γ'-U 2 Mo, α-U phases, and Mo-alloyed γ-U-Mo from the parent γ-U-Mo matrix, along with presence of U-C phase along the grain boundaries. It has been shown previously that discontinuous precipitation (DP) plays a major role during eutectoid transformation in U-10 wt.% Mo at 500 • C and higher [41]. DP results in the formation of a lamellar microstructure consisting of α-U and Mo-enriched bcc γ-U-Mo phase along the prior γ-U-Mo grain boundaries.…”

Section: Evolution Of U-mo Matrixmentioning

confidence: 99%

Microstructural Changes and Chemical Analysis of Fission Products in Irradiated Uranium-7 wt.% Molybdenum Metallic Fuel Using Atom Probe Tomography

et al. 2021

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Understanding the microstructural and phase changes occurring during irradiation and their impact on metallic fuel behavior is integral to research and development of nuclear fuel programs. This paper reports systematic analysis of as-fabricated and irradiated low-enriched U-Mo (uranium-molybdenum metal alloy) fuel using atom probe tomography (APT). This study is carried out on U-7 wt.% Mo fuel particles coated with a ZrN layer contained within an Al matrix during irradiation. The dispersion fuel plates from which the fuel samples were extracted are irradiated at Belgian Nuclear Research Centre (SCK CEN) with burn-up of 52% and 66% in the framework of the SELENIUM (Surface Engineering of Low ENrIched Uranium-Molybdenum) project. The APT studies on U-Mo particles from as-fabricated fuel plates enriched to 19.8% revealed predominantly γ-phase U-Mo, along with a network of the cell boundary decorated with α-U, γ’-U2Mo, and UC precipitates along the grain boundaries. The corresponding APT characterization of irradiated fuel samples showed formation of fission gas bubbles enriched with solid fission products. The intermediate burnup sample showed a uniform distribution of the typical bubble superlattice with a radius of 2 nm arranged in a regular lattice, while the high burnup sample showed a non-uniform distribution of bubbles in grain-refined regions. There was no evidence of remnant α-U, γ’-U2Mo, and UC phases in the irradiated U-7 wt.% Mo samples.

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Section: Evolution Of U-mo Matrixmentioning

confidence: 99%