Finite temperature properties of uranium mononitride

V Kocevski, DA Rehn, AJ Terricabras… - Journal of nuclear …, 2023 - Elsevier
Uranium mononitride (UN) is a promising nuclear fuel that combines the advantageous
properties of readily used UO 2 and uranium alloys, such as high melting temperature and …

Cr-incorporated uranium nitride composite fuels with enhanced mechanical performance and oxidation resistance

K Yang, E Kardoulaki, D Zhao, B Gong… - Journal of Nuclear …, 2022 - Elsevier
Abstract Cr-incorporated UN (Cr-UN) composite fuels with different Cr amounts up to 10 wt%
are fabricated by spark plasma sintering, and their microstructure and phase heterogeneity …

Practical Applications of Gaussian Process with Uncertainty Quantification and Sensitivity Analysis for Digital Twin for Accident-Tolerant Fuel

K Kobayashi, D Kumar, M Bonney, S Alam - Handbook of Smart Energy …, 2022 - Springer
The application of digital twin (DT) technology to the nuclear field is one of the challenges in
the future development of nuclear energy. Possible applications of DT technology in the …

[HTML][HTML] Transient behavior of oxide fuels with controlled microstructure and Cr2O3 additive

D Zhao, H Ban, K Yang, A Broussard, M Li… - npj Materials …, 2024 - nature.com
Microstructure and Cr2O3 doping profoundly impact the thermal-mechanical properties and
fracture of oxides fuels. It is a challenge to study the transient behavior of nuclear fuels under …

Thermal conductivity evaluation of ion irradiated Si3N4 and ZrN ceramics using spatial domain thermoreflectance

AJ Terricabras, J Ferrigno, L Wang… - Journal of Applied …, 2022 - pubs.aip.org
Nitride ceramics have been investigated for different applications in the nuclear industry,
such as space nuclear power, fusion reactor diagnostics and plasma heating, inert matrix …

UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels

B Gong, E Kardoulaki, K Yang, A Broussard… - Ceramics …, 2022 - Elsevier
Abstract Both UN and U 3 Si 2 are potential candidates for accident tolerant fuels due to their
high fissile element density and exceptional thermal conductivity. However, they display a …

New insights into the mechanical and thermal properties of UN1-xCx from first-principles calculations

Y Di, Z He, J Wang - Journal of Nuclear Materials, 2022 - Elsevier
Uranium nitride (UN) is considered to be a very promising candidate of accident-tolerant
fuel. Since UN is commercially synthesized by carbothermic reduction-nitridation, the carbon …

Oxidation susceptibility of UN Σ5 (210) grain boundary with Al/Cr/Ni dopant: A first-principles study

Y Wang, J Zhao, Y Jiang, L Xi, J Zhao - Journal of Nuclear Materials, 2023 - Elsevier
The oxidation susceptibility of UN Σ5 (210) grain boundary (GB) decorated with Al, Cr or Ni
is assessed by first-principles modelling. The predictions show that the low segregation …

Grain growth kinetics of the gamma phase metallic uranium

D Zhao, MT Benson, K Yang, Y Huang… - Journal of Nuclear …, 2023 - Elsevier
Metallic uranium is a leading fuel form for sodium cooled fast reactors as an enabling
technology of future nuclear energy systems. Mechanistic understanding of fuel behaviors …

Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties

D Zhao, MT Benson, T Yao, K Yang… - Journal of Nuclear …, 2023 - Elsevier
To accommodate the swelling of metallic fuels induced by the fission gas release for a
sodium-free fuel option, advanced U-10Zr fuels with controlled porosities were designed …