In Situ Kinetic Observations on Crystal Nucleation and Growth

J Li, FL Deepak - Chemical reviews, 2022 - ACS Publications
Nucleation and growth are critical steps in crystallization, which plays an important role in
determining crystal structure, size, morphology, and purity. Therefore, understanding the …

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 …

In-situ TEM investigation on the evolution of He bubbles and dislocation loops in Ni-based alloy irradiated by H2+ & He+ dual-beam ions

Z Zhu, W Ji, H Huang - Journal of Materials Science & Technology, 2023 - Elsevier
The synergistic evolution mechanisms of He bubbles and dislocation loops under 30 keV H
2+ & H e+ dual-beam ions irradiation at 650° C in the Ni-based alloy GH3535, which is the …

Predicting structural material degradation in advanced nuclear reactors with ion irradiation

S Taller, G VanCoevering, BD Wirth, GS Was - Scientific reports, 2021 - nature.com
Swelling associated with the formation and growth of cavities is among the most damaging
of radiation-induced degradation modes for structural materials in advanced nuclear reactor …

Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2

C Matthews, R Perriot, MWD Cooper, CR Stanek… - Journal of Nuclear …, 2019 - Elsevier
As fission fragments pass through UO 2 nuclear fuel, a considerable concentration of
Frenkel pair defects (ie vacancies and interstitials) are created. The steady-state …

A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten

YG Li, QR Zheng, LM Wei, CG Zhang, Z Zeng - Tungsten, 2020 - Springer
The change in surface damage/microstructures and its effects on the hydrogen (H)
isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten …

[HTML][HTML] Multiscale modelling for fusion and fission materials: The M4F project

L Malerba, MJ Caturla, E Gaganidze, C Kaden… - Nuclear materials and …, 2021 - Elsevier
The M4F project brings together the fusion and fission materials communities working on the
prediction of radiation damage production and evolution and their effects on the mechanical …

A concurrent irradiation-mechanics multiscale coupling model

C Ji, Y Cui, Y Li, N Ghoniem - Journal of the Mechanics and Physics of …, 2022 - Elsevier
The vast majority of our current knowledge regarding the basic mechanisms controlling
irradiation effect on mechanical properties is based almost entirely on the results of post …

Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution

T Barani, D Pizzocri, F Cappia, G Pastore… - Journal of Nuclear …, 2022 - Elsevier
We propose a model describing the high burnup structure inter-granular porosity evolution
under irradiation. The evolution of the porosity collecting the gas diffusing from the grains is …

Data-driven methods for diffusivity prediction in nuclear fuels

GT Craven, R Chen, MWD Cooper, C Matthews… - Computational Materials …, 2023 - Elsevier
The growth rate of structural defects in nuclear fuels under irradiation is intrinsically related
to the diffusion rates of the defects in the fuel lattice. The generation and growth of atomistic …