Oak Ridge National Laboratory Official TM Cover: Development and Qualification of Tungsten Reference Materials for LA-ICP-MS ORNL Report September, 2023
SATS Transient Fission Gas Release Test with Irradiated Fuel under Loss of Coolant Accident Conditions ORNL Report September, 2023
Assessment of Microreactor Safety Analysis Challenges and Recommendations for Utilization of the Comprehensive Reactor Analysis Bundle ORNL Report September, 2023
FY23 Progress Report on Viscosity and Thermal Conductivity Measurements of Molten Salts ORNL Report August, 2023
Mechanical properties of Zircaloy cladding tubes and contributions to M.E.T.A. mechanical property database ORNL Report August, 2023
AMMT FY23 HFIR Irradiation Test Matrix – Supported by the Design of a Miniature Bend Bar Irradiation Vehicle ORNL Report August, 2023
Comparison Between Pin-by Pin Subchannel and System Level Thermal Hydraulic Results for High Burnup Loss-of-Coolant Applications ORNL Report August, 2023