Final Summary Report on the Feasibility and the Benefits of the Advanced Nuclear Fuel Pellet Designs with Radially Varying Fu... ORNL Report July, 2022
Effect of heavy ion irradiation dose rate and temperature on α′ precipitation in high purity Fe-18%Cr alloy Journal June, 2022
Simulation of natural circulation cartridge loop experiments and application to molten salt reactors Journal June, 2022
High-Temperature Tensile and Creep Test Results on Thin Wall Tube Specimens of ODS Alloys 14YWT and OFRAC ORNL Report June, 2022
Coupled Neutronic and Thermal Hydraulic Analysis of a Natural Circulation Based Small Modular Reactor (SMR) using VERA-CS... ORNL Report June, 2022
BISON validation of FeCrAl cladding mechanical failure during simulated reactivity-initiated accident conditions Journal June, 2022
Nonnuclear Experimental Capabilities to Support Design, Development, and Demonstration of Microreactors Journal June, 2022
Improved irradiation resistance of accident-tolerant high-strength FeCrAl alloys with heterogeneous structures Journal June, 2022
