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Kevin G Field
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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
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