Comprehensive Characterization of Helium-Induced Degradation of the Friction Stir Weld on Neutron-Irradiated 304L Stainless Steel ORNL Report October, 2023
Microstructure and in-service degradation of baffle former bolts – in-core components of light water reactors ORNL Report September, 2023
Advanced Multiscale Microscopy Characterization of High Burnup LWR UO2 Before and After LOCA Testing ORNL Report September, 2023
Microstructural Characterizations of Two High Fluence Baffle-Former Bolts Retrieved from a Westinghouse Two-loop Downflow Type PWR ORNL Report September, 2023
Enhanced backscatter and unsaturated blue wavelength shifts in F-doped fused silica optical fibers exposed to extreme neutron... Journal September, 2023
Development of the generation III (ATR generation I) Plutonium-238 production target design Journal September, 2023
SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions ORNL Report September, 2023
Progress on Design and Production of Oxide Dispersion–Strengthened Alumina-Forming Austenitic Alloys for Nuclear Applications ORNL Report September, 2023
Volume 8: Epithermal and Fast Neutron Radiography Facility HFIR Futures – Enhanced Capabilities Series ORNL Report September, 2023
