Anisotropic lattice thermal expansion of uranium-based metallic fuels: A high-temperature X-ray diffraction study

Park, Jeongmi; Cho, Su Yeon; Youn, Young-Sang; Lee, Jeongmook; Kim, Jong-Yun; Park, Seo-Hyeon; Bae, Sang-Eun; Kuk, Seoung Woo; Park, Jeong-Yong; Rhee, Choong Kyun; Lim, Sang Ho

doi:10.1016/j.jnucmat.2019.151803

Cited by 6 publications

(1 citation statement)

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“…On the U-Zr phase diagram (Figure 1), under equilibrium conditions, U-10Zr fuel should consist of a mixture of α-U and δ-UZr 2 phases. X-ray diffraction, however, failed to detect the δ-UZr 2 phase (Park et al, 2019). Furthermore, scanning electron microscopy (SEM) characterization showed the microstructure of U-10Zr fuel is uniform despite the large Zr precipitates that were not predicted by the U-Zr phase diagram.…”

Section: Introductionmentioning

confidence: 99%

The advanced characterization, post-irradiation examination, and materials informatics for the development of ultra high-burnup annular U-10Zr metallic fuel

et al. 2023

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U-Zr metallic fuel is a promising fuel candidate for Gen Ⅳ fast spectrum reactors. Previous experimental irradiation campaigns showed that the sodium thermal bonded U-10Zr fuel design can achieve a burnup of 10% fissions per initial heavy metal atom (FIMA). Advanced metallic fuel designs are pushing the burnup limit to 20% or even 30% FIMA. To achieve the higher burnup and eliminate the pyrophoric sodium, a prototypical annular fuel has been designed, fabricated, clad with HT-9 in the Materials and Fuels Complex, and irradiated in the Advanced Test Reactors of Idaho National Laboratory (INL) to a peak burnup of 3.3% FIMA. During irradiation, the mechanical contact between fuel and cladding acts as a thermal bond. The irradiation lasted for 132 days in the reactor. Recently, the archived fresh and irradiated fuel samples were characterized using advanced characterization capabilities in the Irradiated Materials Characterization Laboratory (IMCL) of INL. This article summarizes the results of advanced characterization and computer vision-based materials informatics to reveal the irradiation effects on U-Zr metallic fuel. Future work will focus on further implementation of advanced characterization and statistical data mining to improve the fidelity of fuel performance modeling and support U-Zr metallic fuel qualification for fast spectrum reactors.

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Section: Introductionmentioning

confidence: 99%