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Fracture_Toughness_Characterization_of_Highly_Irradiated_Reactor_Pressure_Weld_from_the_ATR-2_Experiment.pngFracture_Toughness_Characterization_of_Highly_Irradiated_Reactor_Pressure_Weld_from_the_ATR-2_Experiment372 x 479110 KB 10/16/2018 9:11 AMFracture Toughness Characterization of Highly Irradiated Reactor Pressure Weld from the ATR-2 Experiment
Implementation_of_ANL_Mechanics_Based_Evolutionary.pngImplementation_of_ANL_Mechanics_Based_Evolutionary372 x 48134 KB 11/14/2018 12:50 PMImplementation of ANL’s Mechanics Based Evolutionary Fatigue Modeling Through ABAQUSWARP3D Based HPC Framework Modeling
Interdigital_Capacitance_Local_NDE_of_NPP.pngInterdigital_Capacitance_Local_NDE_of_NPP372 x 481114 KB 10/17/2018 3:57 PMhttps://lwrsdev.inl.gov/ReportImages/Interdigital_Capacitance_Local_Non-Destructive_Examination_of_Nuclear_Power_Plant.png
Investigation_of_Thermal_Aging_Behavior_for_Harvested.pngInvestigation_of_Thermal_Aging_Behavior_for_Harvested372 x 481116 KB 10/16/2018 9:12 AMhttp://nuc.inl.gov
Metallurgical_Aspects_Influencing_the_Resistance.pngMetallurgical_Aspects_Influencing_the_Resistance372 x 480113 KB 10/16/2018 7:22 AMhttps://lwrsdev.inl.gov/ReportImages/Metallurgical_Aspects_Influencing_the_Resistance_to_Steam_Oxidation_r1.png
ReportofProgress.pngReportofProgress372 x 481163 KB 11/14/2018 12:52 PMReport on the Progress of Weld Development of Irradiated Materials at the Oak Ridge National Laboratory
Stress_Corrosion_Crack_Initiation_and_Propagation.pngStress_Corrosion_Crack_Initiation_and_Propagation372 x 481138 KB 10/16/2018 9:13 AMhttps://lwrsdev.inl.gov/RecentTechnicalReports/Stress_Corrosion_Crack_Initiation_and_Propagation_under_Different_Corrosion_Environments_and_the_Role_of_Post-Irradiation.pdf
Thermodynamic_and_kinetic_model_of_phase_stability_in_austenitic_steel_under_light_water_reactor_conditions.pngThermodynamic_and_kinetic_model_of_phase_stability_in_austenitic_steel_under_light_water_reactor_conditions369 x 478105 KB 10/17/2018 3:51 PMThermodynamic and kinetic model of phase stability in austenitic steel under light water reactor conditions