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Kevin G. Field
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A deep learning based automatic defect analysis framework for In-situ TEM ion irradiations
Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
STEM Characterization of Dislocation Loops in Irradiated FCC Alloys
Microstructural characterization of cold-worked 316 stainless steel flux thimble tubes irradiated up to 100 dpa in a commercial Pressurized Water Reactor
Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature
High-Efficiency Three-Dimensional Visualization of Complex Microstructures via Multidimensional STEM Acquisition and Reconstruction
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding
Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature
Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy
Perspectives on the FESAC transformative enabling capabilities: Priorities, plans, and Status
Radiation Effects in FeCrAl Alloys for Nuclear Power Applications
Rapid Characterization Methods for Accelerated Innovation for Nuclear Fuel Cladding
Accident tolerant fecral fuel cladding: current status towards commercialization
Distinct effects of irradiation on the structure and chemical reactivity of silicates and carbonates
Evaluation of post-weld heat treatments applied to FeCrAl alloy weldments
Evaluation of the continuous dilatometer method of silicon carbide thermometry for passive irradiation temperature determination
Influence of welding and neutron irradiation on dislocation loop formation and $\alpha$′ precipitation in a FeCrAl alloy
Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing
Post irradiation examination of nanoprecipitate stability and $\alpha$′ precipitation in an oxide dispersion strengthened Fe-12Cr-5Al alloy
Automated defect analysis in electron microscopic images
Designing for radiation tolerance in fecral alloys
Mechanical performance of neutron-irradiated dissimilar transition joints of aluminum alloy 6061-T6 and 304L stainless steel
Precipitation of $\alpha$′ in neutron irradiated commercial FeCrAl alloys
Radiation-induced degradation of concrete in NPPs
Role of refractory inclusions in the radiation-induced microstructure of APMT
A combined APT and SANS investigation of $\alpha$′ phase precipitation in neutron-irradiated model FeCrAl alloys
Characterization of Radiation Fields for Assessing Concrete Degradation in Biological Shields of NPPs
Characterization of Radiation Fields for Assessing Concrete Degradation in Biological Shields of NPPs
Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys
Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
Impact of neutron irradiation on thermal helium desorption from iron
Mechanical performance of RAFM and ODS steels in HFIR JP28 and JP29 irradiations
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing
Synergies Between $\alpha$' and Cavity Formation in HT-9 Following High Dose Neutron Irradiation
Synergies Between $\alpha$' and Cavity Formation in HT-9 Following High Dose Neutron Irradiation
Complementary Techniques for Quantification of $\alpha$' Phase Precipitation in Neutron-Irradiated Fe-Cr-Al Model Alloys
Complementary Techniques for Quantification of $\alpha$' Phase Precipitation in Neutron-Irradiated Fe-Cr-Al Model Alloys
Correlative microscopy of neutron-irradiated materials
Database on Performance of Neutron Irradiated FeCrAl Alloys
Dependencies of $\alpha$' embrittlement in neutron-irradiated model Fe-Cr-Al alloys
Direct Experimental Evidence for Differing Reactivity Alterations of Minerals following Irradiation: The Case of Calcite and Quartz
Microscopy of Plasma-Materials Interactions in Tungsten for Fusion Power
Overview of the multifaceted activities towards development and deployment of nuclear-grade FeCrAl alloys
Recent Advances in Analytical Electron Microscopy for Irradiated Materials
Recent Advances in Analytical Electron Microscopy for Irradiated Materials
Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe-Cr-Ni alloys
Status Report on Irradiation Capsules Containing Welded FeCrAl Specimens for Radiation Tolerance Evaluation
The Analysis of the General Performance and Mechanical Behavior of Unirradiated FeCrAl Alloys Before and After Welding
The Analysis of the General Performance and Mechanical Behavior of Unirradiated FeCrAl Alloys Before and After Welding
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature
Current status of FeCrAl alloys as an accident tolerant cladding alloy class for commercial light water reactors
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments
Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels
Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels
Effect of exposure environment on surface decomposition of SiC-silver ion implantation diffusion couples
LAMDA: A facility for advanced characterization of irradiated materials at Oak Ridge national laboratory
LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory
Role of scale factor during tensile testing of small specimens
Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications
Degradation of concrete for nuclear structures: Identified mechanisms and knowledge gaps
Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel
Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9 wt.\% Cr model ferritic/martensitic steel
Concrete aging and degradation in NPPs: LWRS program R\&D progress report
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.\% Cr model ferritic/martensitic steel
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.\% Cr model ferritic/martensitic steel
FY-13 FCRD Milestone M3FT-13OR0202311 Weldability of ORNL Accident Tolerant Fuel Cladding Model Alloys For Thin Walled Tubes
Formation of biomimetic porous calcium phosphate coatings on surfaces of polyethylene/zinc stearate Blends
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