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Status Report on the Fabrication of Fuel Cladding Chemical Interaction Test Articles for ATR Irradiations

FY-14 FCRD Milestone: M3FT-14OR0202232 FCRD Advanced Fuels Campaign (AFC) Level 3 Milestone Report Letter Report Documenting Progress of Second Generation ATF FeCrAl Alloy Fabrication

Development of the 2 nd generation ATF FeCrAl alloy has been initiated, and a candidate alloy was selected for trial tube fabrication through hot-extrusion and gun-drilling processes. Four alloys based on Fe-13Cr-4.5Al-0.15Y in weight percent were …

Phase stability and mechanical properties of nuclear grade FeCrAl Under LWR-relevant neutron irradiation

This study will be utilized to investigate the formation of a' phases and quantify the number density and average diameter if a' precipitation was detected. PIE will assist with determining the contributions of Cr, Al, and Y to the phase stability …

Stability of Model Fe-Cr-Al Alloys Under The Presence of Neutron Radiation

FY-13 FCRD Milestone M3FT-13OR0202311 Weldability of ORNL Accident Tolerant Fuel Cladding Model Alloys For Thin Walled Tubes

Microchemical variations in proton irradiated 9 wt.\% chromium BCC steels