Micromechanical modeling of single crystal and polycrystalline UO2 at elevated temperatures

Article Mechanics

Viscoplastic behavior of a porous polycrystal with similar pore and grain sizes: Application to nuclear MOX fuel materials

Luc Portelette et al.

Summary: The study investigates the viscoplastic behavior of a porous polycrystal with pores and grains of similar sizes. The relative size of pores plays a minor role in the overall viscoplastic behavior compared to the size of grains.

INTERNATIONAL JOURNAL OF SOLIDS AND STRUCTURES (2022)

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Article Materials Science, Multidisciplinary

Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets

Murali Krishna Tummalapalli et al.

Summary: In this study, UO2-Mo samples were fabricated using spark plasma sintering method and the thermophysical properties were experimentally analyzed, including the relationship between thermal diffusivity and thermal conductivity with temperature, and the effects of density and grain size on the thermophysical properties.

JOURNAL OF NUCLEAR MATERIALS (2022)

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Article Engineering, Mechanical

Micromorphic crystal plasticity approach to damage regularization and size effects in martensitic steels

Matti Lindroos et al.

Summary: The reduced micromorphic model introduces an additional microvariable to regulate localized inelastic deformation mechanisms, formulates damage as a strain-like variable, and investigates strategies for treating slip and damage as non-local variables. The model accounts for size-effects and predicts finite width damage localization bands, introducing extra-hardening near grain boundaries and slip localization zones. Two approaches for dealing with damage localization are identified: indirect method based on controlling slip bands width and direct method in which damage flow is regularized together with or separately from plastic slip. Application to a real martensitic steel microstructure is explored.

INTERNATIONAL JOURNAL OF PLASTICITY (2022)

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Article Materials Science, Multidisciplinary

Brittle fracture initiation in decommissioned boiling water reactor pressure vessel head weld

Zaiqing Que et al.

Summary: This study investigates the brittle fracture initiation behavior and fracture toughness of a thermally-aged weld metal in a decommissioned reactor pressure vessel head. The results reveal that brittle fracture primarily originates from non-metallic inclusions. The correlation between fracture toughness and various factors such as initiation type, size, and location is analyzed.

JOURNAL OF NUCLEAR MATERIALS (2022)

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Article Materials Science, Multidisciplinary