The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxygen distribution, and composite specimens with a ZrO2/alpha/beta layer structure was investigated over the range of experimental conditions: temperature 25-1400 degrees C; strain rate ; oxygen content 0.11 - 4.4 wt %; grain size 5-50 micrometers; texture longitudinal, transverse, and diagonal orientations; and microstructural state, which consists of the equiaxed alpha phase and various transformed beta acicular structures. The work-hardening and strain-rate sensitivity parameters were determined from the experimental results, and the tensile properties were correlated with oxygen concentration, oxygen distribution in the material, and microst...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenario, zirconium alloy ...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
The solute strengthening due to oxygen in Zircaloy-2 was investigated over the temperature range 102...
International audienceIt is now well acknowledged that, after a prototypical loss of coolant acciden...
The effect of temperature and strain-rate on the yield and flow stress of zirconium, containing oxyg...
The anomalous strain rate sensitivity of zirconium alloys over the temperatures range 20C–600° has b...
Oxidation tests were conducted at 450 degrees C in air for Zircaloy-2 and modified alloys. The resul...
Zirconium alloys are routinely used as cladding material in the nuclear industry due to the favorabl...
The hot-working characteristics of Zircaloy-2 have been studied in the temperature range of 650 to 9...
The yielding and fracture characteristics of Zircaloy-2 as a function of stress slate were investiga...
Development of physically-based constitutive models capable of simultaneously describing slip, twinn...
The hot-working characteristics of Zircaloy-2 have been studied in the temperature range of 650 to 9...
Extensive plastic deformation in the metal underneath the oxide scale in autoclave tested Zircaloy-2...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenario, zirconium alloy ...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
The solute strengthening due to oxygen in Zircaloy-2 was investigated over the temperature range 102...
International audienceIt is now well acknowledged that, after a prototypical loss of coolant acciden...
The effect of temperature and strain-rate on the yield and flow stress of zirconium, containing oxyg...
The anomalous strain rate sensitivity of zirconium alloys over the temperatures range 20C–600° has b...
Oxidation tests were conducted at 450 degrees C in air for Zircaloy-2 and modified alloys. The resul...
Zirconium alloys are routinely used as cladding material in the nuclear industry due to the favorabl...
The hot-working characteristics of Zircaloy-2 have been studied in the temperature range of 650 to 9...
The yielding and fracture characteristics of Zircaloy-2 as a function of stress slate were investiga...
Development of physically-based constitutive models capable of simultaneously describing slip, twinn...
The hot-working characteristics of Zircaloy-2 have been studied in the temperature range of 650 to 9...
Extensive plastic deformation in the metal underneath the oxide scale in autoclave tested Zircaloy-2...
International audienceDuring hypothetical Loss-Of-Coolant-Accident (LOCA) scenario, zirconium alloy ...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
International audienceDuring hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear ...