Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel

Hiezl, Zoltan; Hambley, David; Padovani, Cristiano; Lee, William

doi:10.1016/j.jnucmat.2014.09.002

Cited by 15 publications

(2 citation statements)

References 26 publications

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“…Precipitation of alloy particles not only depends on atomic concentrations, but also the mobilities in a matrix. In fact, the calculated atomic ratio of Ru to Mo is 0.80 for 43 GW d/t U after 100 years cooling time 17 as compared to 0.75 in this study. Pd has been found to be the most mobile element among the five dopants in CeO 2 .…”

Section: Resultssupporting

confidence: 54%

In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

et al. 2019

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Metallic particles formed in oxide fuels (e.g., UO 2 ) during neutron irradiation have an adverse impact on fuel performance. A fundamental investigation of particle precipitation is needed to predict the fuel performance and potentially improve fuel designs and operations. This study reports on the precipitation of Mo-dominant β-phase particles in polycrystalline CeO 2 (surrogate for UO 2 ) films doped with Mo, Pd, Rh, Ru, and Re (surrogate for Tc). In situ heating scanning transmission electron microscopy indicates that particle precipitation starts at ∼1073 K with a limited particle growth to ∼10 nm. While particle concentration increases with increasing temperature, particle size remains largely unchanged up to 1273 K. There is a dramatic change in the microstructure following vacuum annealing at 1373 K, probably due to phase transition of reduced cerium oxide. At the high temperature, particles grow up to 75 nm or larger with distinctive facets. The particles are predominantly composed of Mo with a body-centered cubic structure (β phase). An oxide layer was observed after storage at ambient conditions. In situ heating X-ray photoelectron spectroscopy reveals an increasing reduction of Ce charge state from 4+ to 3+ in the doped CeO 2 film at temperatures from 673 to 1273 K. In situ ion irradiation transmission electron microscopy with 2 MeV Al 2+ ions up to a dose of ∼20 displacements per atom at nominally room temperature does not lead to precipitation of visible particles. However, irradiation with 1.7 MeV Au 3+ ions to ∼10 dpa at 973 K produces ∼2 nm sized pure Pd particles; Au 3+ irradiation at 1173 K appears to result in precipitates of ∼6 nm in size. Some of the defects produced by ion irradiation could be nucleation sites for precipitation, leading to generation of smaller particles with a higher concentration.

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Section: Resultssupporting

confidence: 54%

In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

et al. 2019

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“…Previously FISPIN has been used by Hiezl et al (2015) [29] for the characterization of a UO2spent fuel for disposal studies on spent AGR fuel and for estimating the chemistry and physics of modeling nitride fuels for transmutation, see Thetford & Mignanelli (2003) [21]. It has been used by Mills et al (2020) [30] discussing the main issues concerning the fission product build up during burnup but also many interesting issues concerning the behavior and performances of the fuel in pile and as an antineutrino source.…”

Section: Data Librariesmentioning

confidence: 99%

Simulation of uranium mononitride spent fuel: A crystallographic approach

Degueldre

Goddard

Berhane

et al. 2022

Journal of Nuclear Materials

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Physical characterization of uranium oxide pellets and powder applied in the Nuclear Forensics International Technical Working Group Collaborative Materials Exercise 4

Griffiths

Keegan

Young

et al. 2018

J Radioanal Nucl Chem

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Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel

Cited by 15 publications

References 26 publications

In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

Simulation of uranium mononitride spent fuel: A crystallographic approach

Physical characterization of uranium oxide pellets and powder applied in the Nuclear Forensics International Technical Working Group Collaborative Materials Exercise 4

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Processing and microstructural characterisation of a UO2-based ceramic for disposal studies on spent AGR fuel

Cited by 15 publications

References 26 publications

In Situ Study of Particle Precipitation in Metal-Doped CeO2 during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

In Situ Study of Particle Precipitation in Metal-Doped CeO2 during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

Simulation of uranium mononitride spent fuel: A crystallographic approach

Physical characterization of uranium oxide pellets and powder applied in the Nuclear Forensics International Technical Working Group Collaborative Materials Exercise 4

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Product

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In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels

In Situ Study of Particle Precipitation in Metal-Doped CeO₂ during Thermal Treatment and Ion Irradiation for Emulation of Irradiating Fuels