Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient Journal October, 2023
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
SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions ORNL Report September, 2023
Volume 8: Epithermal and Fast Neutron Radiography Facility HFIR Futures – Enhanced Capabilities Series ORNL Report September, 2023
AFC FY 2023 HFIR Irradiation Test Matrix – Supported by the Design of a Ring Specimen Irradiation Vehicle ORNL Report September, 2023
Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding Journal August, 2023
