Thermal conductivity evaluation of high burnup mixed-oxide (MOX) fuel pellet
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference19 articles.
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2. Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications;Journal of Nuclear Materials;2020-12
3. Mesoscale Thermal Transport Measurements of Multi-phase and Porous Nuclear Fuels Using a Square-wave Pulse Thermoreflectance Technique;Microscopy and Microanalysis;2020-07-30
4. Determining local thermal transport in a composite uranium-nitride/silicide nuclear fuel using square-pulse transient thermoreflectance technique;Journal of Nuclear Materials;2020-01
5. Molecular dynamics modelling of the thermal conductivity of off-stoichiometric UO2±x and (UyPu1−y)O2±x using equilibrium molecular dynamics;Annals of Nuclear Energy;2019-09
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