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 …

A review of Calphad modeling of ordered phases

B Sundman, Q Chen, Y Du - Journal of Phase Equilibria and Diffusion, 2018 - Springer
The models used in Calphad to describe long and short range ordering in multicomponent
alloys have improved significantly over the last 20 years. For long range ordering the …

[图书][B] Computational thermodynamics: the Calphad method

H Lukas, SG Fries, B Sundman - 2007 - dl.acm.org
Phase diagrams are used in materials research and engineering to understand the
interrelationship between composition, microstructure and process conditions. In complex …

[图书][B] Comprehensive nuclear materials

R Konings, RE Stoller - 2020 - books.google.com
Materials in a nuclear environment are exposed to extreme conditions of radiation,
temperature and/or corrosion, and in many cases the combination of these makes the …

Uranium

I Grenthe, J Drożdżynński, T Fujino, EC Buck… - The chemistry of the …, 2006 - Springer
By 1911, the atomic weight of uranium had been refined to 238.5 (Gmelin, vol. A2, 1980a).
The natural isotope 235 U was discovered in 1935 by mass spectrometry. The artificial …

Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

C Guéneau, N Dupin, B Sundman, C Martial… - Journal of nuclear …, 2011 - Elsevier
In the present work a thermodynamic model is derived for the (U, Pu) O2 oxide, the (U, Pu) C
carbide fuels using the Calphad method to describe consistently both phase diagrams and …

TAF-ID: An international thermodynamic database for nuclear fuels applications

C Gueneau, N Dupin, L Kjellqvist, E Geiger, M Kurata… - Calphad, 2021 - Elsevier
Abstract The Thermodynamics of Advanced Fuels–International Database (TAF-ID) was
developed using the Calphad method to provide a computational tool to perform …

Accurate lattice parameter measurements of stoichiometric uranium dioxide

G Leinders, T Cardinaels, K Binnemans… - Journal of Nuclear …, 2015 - Elsevier
The paper presents and discusses lattice parameter analyses of pure, stoichiometric UO 2.
Attention was paid to prepare stoichiometric samples and to maintain stoichiometry …

Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x: Implications for nuclear fuel performance modeling

DA Andersson, P Garcia, XY Liu, G Pastore… - Journal of Nuclear …, 2014 - Elsevier
Based on density functional theory (DFT) and empirical potential calculations, the diffusivity
of fission gas atoms (Xe) in UO 2 nuclear fuel has been calculated for a range of non …

Melting of stoichiometric and hyperstoichiometric uranium dioxide

D Manara, C Ronchi, M Sheindlin, M Lewis… - Journal of Nuclear …, 2005 - Elsevier
The solid–liquid transition in stoichiometric and hyperstoichiometric UO2 was investigated
by means of advanced techniques. Laser heating enabling fast melting and freezing …