Nanoindentation measurements of the mechanical properties of zirconium matrix and hydrides in unirradiated pre-hydrided nuclear fuel cladding - Concepedia

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Nanoindentation measurements of the mechanical properties of zirconium matrix and hydrides in unirradiated pre-hydrided nuclear fuel cladding

47

Citations

19

References

2014

Year

A. Rico, M. A. Martín-Rengel, J. Ruiz-Hervías, J. Rodrı́guez, F.J. Gómez

Journal of Nuclear Materials

Materials ScienceZirconium MatrixEngineeringMechanical PropertiesMechanical EngineeringMaterial ModelingNanoindentation MeasurementsMicrostructure-strength RelationshipMaterial PerformanceHydrogen EmbrittlementMicrostructure

References

	Year	Citations

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