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 …

Study of thermodynamic properties of U1-yPuyO2 MOX fuel using classical molecular Monte Carlo simulations

C Takoukam-Takoundjou, E Bourasseau… - Journal of Nuclear …, 2020 - Elsevier
Abstract The molecular Monte Carlo method, combined with the CRG interatomic potential,
is used for the first time to investigate stoichiometric mixed oxides U 1-y Pu y O 2 (with y in …

Thermal transport crossover from crystalline to partial-crystalline partial-liquid state

Y Zhou, S Xiong, X Zhang, S Volz, M Hu - Nature communications, 2018 - nature.com
Phase-change materials (crystalline at low temperatures and partial-crystalline partial-liquid
state at high temperatures) are widely used as thermoelectric converters and battery …

Superionic UO2: A model anharmonic crystalline material

H Zhang, X Wang, A Chremos… - The Journal of chemical …, 2019 - pubs.aip.org
Crystalline materials at elevated temperatures and pressures can exhibit properties more
reminiscent of simple liquids than ideal crystalline materials. Superionic crystalline materials …

Assessment of empirical potential for MOX nuclear fuels and thermomechanical properties

H Balboa, L Van Brutzel, A Chartier… - Journal of Nuclear …, 2017 - Elsevier
We assess five empirical interatomic potentials in the approximation of rigid ions and pair
interactions for the (U 1− y, Pu y) O solid solution. The assessment compares available …

Structure and Thermal Expansion of YSZ and La2Zr2O7 Above 1500°C from Neutron Diffraction on Levitated Samples

SV Ushakov, A Navrotsky, RJK Weber… - Journal of the …, 2015 - Wiley Online Library
High‐temperature time‐of‐flight neutron diffraction experiments were performed on cubic
yttria‐stabilized zirconia (YSZ, 10 mol% YO1. 5) and lanthanum zirconate (LZ) prepared by …

Melting behavior of (Th, U) O2 and (Th, Pu) O2 mixed oxides

PS Ghosh, N Kuganathan, COT Galvin, A Arya… - Journal of Nuclear …, 2016 - Elsevier
The melting behaviors of pure ThO 2, UO 2 and PuO 2 as well as (Th, U) O 2 and (Th, Pu) O
2 mixed oxides (MOX) have been studied using molecular dynamics (MD) simulations. The …

Glide mobility of the 1/2 [1 1 0](0 0 1) edge dislocation in UO2 from molecular dynamics simulation

AV Lunev, AY Kuksin, SV Starikov - International Journal of Plasticity, 2017 - Elsevier
Both the mechanical properties of oxide nuclear fuel and the high burn-up grain
restructuring are known to be related to dislocation motion. Previous studies show that at …

First-principles calculation study on phonon thermal conductivity of thorium and plutonium dioxides: Intrinsic anharmonic phonon-phonon and extrinsic grain-boundary …

H Nakamura, M Machida - Journal of Nuclear Materials, 2019 - Elsevier
In nuclear engineering, thermal conductivity of nuclear fuel materials is one of the most
essential thermophysical data in analyzing nuclear reactor safety and fuel performance. In …

Molecular Dynamics study of the effects of non-stoichiometry and oxygen Frenkel pairs on the thermal conductivity of uranium dioxide

S Nichenko, D Staicu - Journal of nuclear materials, 2013 - Elsevier
In the present work, calculations of the thermal conductivity of UO2 were carried out applying
classical Molecular Dynamics for the isothermal-isobaric (NPT) statistical ensemble, using …