International Journal of Damage Mechanics · 2020 · 19 citations · 32 references
EngineeringMaterials EngineeringMaterials ScienceFinite Element AnalysisMechanical Behavior Of MaterialsThermodynamicsCeramic Matrix CompositesComputational ThermomechanicsDamage MechanicsFracture MechanicsRadiation Damage In MaterialsThermal Properties Of MaterialsContinuum Damage MechanicsContinuum Damage ModelsIrradiation EffectsNeutron Irradiation DamageNeutron Irradiation EffectsThermal ConductivityThermo-mechanical CouplingThermo-mechanical Modelling
A damage model is developed and validated with experimental data for the non-linear mechanical behavior of SiC/SiC composite materials in nuclear applications. Cyclic thermal and mechanical loading associated with neutron irradiation effects of these composites leads to wide-spread and progressive micro-cracking that leads to loss of thermal conductivity and further enhancement of thermo-mechanical damage. A physics-based model of wide-spread micro-cracking is developed within the thermodynamic framework of continuum damage mechanics. Evolution equations for damage parameters that describe the growth of continuum damage are developed, where the material variables are obtained from experiments. The model novelty is in coupling mechanical, thermal, and irradiation damage through a consistent thermodynamic framework, including loss of thermal conductivity due to the evolution of mechanically induced micro-cracks. A number of thermo-mechanical experiments were conducted to confirm model assumptions. The model is shown to be validated with out-of-pile experiments, and then implemented using commercial finite element code COMSOL to the fuel cladding problem with normal and high radiation dose cases.
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Handbook of SiC properties for fuel performance modeling
Lance L. Snead, Takashi Nozawa, Yutai Katoh et al. · Journal of Nuclear Materials · 2007 · 1.4K citations
Materials challenges for nuclear systems
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