Kevin G Field

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3D printed features on nuclear fuel cladding for optimized heat transfer
Accelerating Domain-Aware Electron Microscopy Analysis Using Deep Learning Models with Synthetic Data and Image-Wide Confidence Scoring
Extending damage accumulation of commercial reactor irradiated 316 stainless steel with ion irradiation
MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Self-ion irradiation effects on phase stability
Evaluation of Human-Bias in Labeling of Ambiguous Features in Electron Microscopy Machine Learning Models
FeCrAl fuel/clad chemical interaction in light water reactor environments
Materials swelling revealed through automated semantic segmentation of cavities in electron microscopy images
Systematic study of radiation-induced segregation in neutron-irradiated FeCrAl alloys
Corrigendum to" Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
Creep behavior of an additively manufactured 9Cr steel in the as-built condition
Effect of N2-and CO2-containing shielding gases on composition modification and carbonitride precipitation in wire arc additive manufactured grade 91 steel
Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures
Investigation of deformation mechanisms in an advanced FeCrAl alloy using in-situ SEM-EBSD testing
Microchemical evolution of irradiated additive-manufactured HT9
Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Real-time, On-Microscope Automated Quantification of Features in Microcopy Experiments Using Machine Learning and Edge Computing
Towards Optimized Characterization of Dislocation Loops in Irradiated FCC Alloys Using On-Zone STEM Techniques
A deep learning based automatic defect analysis framework for In-situ TEM ion irradiations
An Open Analysis Platform with In-Situ Machine Vision for Electron Microscopy Final Technical Report
Deconvoluting the effect of chromium and aluminum on the radiation response of wrought FeCrAl alloys after low-dose neutron irradiation
Development and deployment of automated machine learning detection in electron microcopy experiments
Dislocation loops in proton irradiated uranium-nitrogen-oxygen system
FeCrAl Accident Tolerant Fuel Cladding: Insights from a Decade of Development
Fracture Toughness Characterization of Generation II FeCrAl Alloys after\~ 18 dpa Irradiation
Irradiation-induced amorphization of Fe-Y-based second phase particles in accident-tolerant FeCrAl alloys
Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment
Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing
Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa
STEM characterization of dislocation loops in irradiated FCC alloys
Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing
Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR
Detection of Open Loop Defects in STEM Images of Irradiation-Damaged Alloys--Source Code for Detection and Image Dataset
Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1.1) Prepared for U.S. Department of Energy Nuclear Technology R\&D Advanced Fuels Campaign FY18 version author(s): Kevin G. Field 1 FY17 version author(s)
High Temperature Mechanical Properties of HFIR Irradiated FeCrAl Alloys
Multi-modal STEM-based tomography of HT-9 irradiated in FFTF
Preliminary Characterization and Mechanical Performance of Additively Manufactured HT9
Deformation Behavior in Neutron Irradiated Generation II FeCrAl Alloys for Accident Tolerant Fuel Cladding
Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
Irradiation of Wrought FeCrAl Tubes in the High Flux Isotope Reactor
Irradiation Testing of Accident Tolerant Fuel FeCrAl Cladding
Microstructural stability of irradiated Fe-Cr-Al alloys for fuel cladding applications.
ORNL/TM-2017/186 Rev.1 Handbook of FeCrAl Alloys for Nuclear Power Production Applications
ORNL/TM-2017/186 Rev.1 Handbook of FeCrAl Alloys for Nuclear Power Production Applications
Radiation Induced Segregation at Low Angle Grain Boundaries in Steels NSUF 2017 Milestone Report
Radiation Induced Segregation at Low Angle Grain Boundaries in Steels NSUF 2017 Milestone Report
Status of Wrought FeCrAl-UO2 Capsules Irradiated in the Advanced Test Reactor
Effect of Alloying Additions on Wrought FeCrAl Alloys for Accident-Tolerant Fuel Cladding
Post-deformation examination of specimens subjected to SCC testing
Status of FeCrAl ODS Irradiations in the High Flux Isotope Reactor
Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules
Status Report on Irradiation Capsules Designed to Evaluate FeCrAl-UO2 Interactions
Submission of FeCrAl Feedstock for Support of AFC ATR- 2 Irradiations
Evaluation of the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys, ORNL/TM-2015/518 M2FT-15OR02302243
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys
Preliminary Results on FeCrAl Alloys in the As-received and Welded State Designed to Have Enhanced Weldability and Radiation Tolerance
Preliminary Results on FeCrAl Alloys in the As-received and Welded State Designed to Have Enhanced Weldability and Radiation Tolerance
Radiation Tolerance of Neutron-Irradiated Model Fe-Cr-Al Alloys
Status Report on the Fabrication of Fuel Cladding Chemical Interaction Test Articles for ATR Irradiations
Analysis of Phase Transformation Studies in Solute Addition Alloys
Radiation Induced Segregation in High Chromium Ferritic / Martensitic Steels By