Thermal energy transport in oxide nuclear fuel

DH Hurley, A El-Azab, MS Bryan, MWD Cooper… - Chemical …, 2021 - ACS Publications
To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …

Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel

D Salvato, CA Smith, TR Pavlov, WA Hanson… - Journal of Nuclear …, 2024 - Elsevier
Advanced microstructural characterization techniques, such as scanning electron
microscopy (SEM) and scanning transmission electron microscopy-energy dispersive x-ray …

Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation

L He, M Khafizov, C Jiang, B Tyburska-Püschel… - Acta Materialia, 2021 - Elsevier
Uranium mononitride (UN) with 5 wt.% uranium dioxide (UO 2) is used as a model system to
study the phase and defect evolution under proton irradiation in nitride-oxide composite …

Nanocrystalline ZrN thin film development via atomic layer deposition for U-Mo powder

S Bhattacharya, L Jamison, DN Seidman… - Journal of Nuclear …, 2019 - Elsevier
Zirconium nitride (ZrN) thin film deposited via thermal atomic layer deposition (ALD) has
been recently chosen as a candidate technology for application of a diffusion barrier coating …

Electro-brush plating Ni-Graphene oxide composite coating enhanced corrosion resistance of fluoride ion

P Xu, X Shen, G Xin - Materials Research Express, 2021 - iopscience.iop.org
Abstract Ni-Graphene Oxide (GO) composite coating was prepared on Q235 steel plate by
electro-brush plating technique to reduce the corrosion of fluoride ion. In this study, SEM …

[HTML][HTML] Oxidation of a zirconium nitride multilayer-covered knee implant after two years in clinical use

JS Rau, G Eriksson, P Malmberg, ALP Reyna… - Acta Biomaterialia, 2024 - Elsevier
The surface composition and microstructure of an up to 5 µm thick multilayer on a knee
implant were investigated. When the implant was explanted after approximately two years of …

Synchrotron micro-computed tomography analysis of neutron-irradiated U-Mo fuel

AF Bengoa, J Thomas, J Hunter, P Kenesei… - Journal of Nuclear …, 2024 - Elsevier
Abstract The three-dimensional (3D) microstructure of neutron-irradiated uranium-10 wt.%
molybdenum (U-10Mo) fuel with a burn-up of 9.8× 10 21 fissions/cm 3 was characterized …

A novel approach to determine the local burnup in irradiated fuels using Atom Probe Tomography (APT)

M Bachhav, J Gan, D Keiser, J Giglio… - Journal of Nuclear …, 2020 - Elsevier
A novel approach is presented to determine the local burnup in irradiated fuels using
isotopic quantification obtained by Atom Probe Tomography (APT). Considering the volume …

Microstructural changes and chemical analysis of fission products in irradiated uranium-7 wt.% molybdenum metallic fuel using atom probe tomography

M Bachhav, B Miller, J Gan, D Keiser, A Leenaers… - Applied Sciences, 2021 - mdpi.com
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 …

ZrN coating as diffusion barrier in U (Mo) dispersion fuel systems

A Leenaers, B Ye, J Van Eyken… - Journal of Nuclear …, 2021 - Elsevier
The control of the interaction between the U (Mo) fuel phase and the Al matrix is one of the
challenges of dispersion fuel plate development for research reactors. Given the specific …