Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety Journal December, 2020
Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing... Journal December, 2020
A Critical Review of High Burnup Fuel Fragmentation, Relocation, and Dispersal under Loss-Of-Coolant Accident Conditions Journal December, 2020
Initial Embedding of Functional Sensors in Additively Manufactured Silicon Carbide Conference Paper November, 2020
Post-Irradiation Examination Supporting the Transformational Challenge Reactor Conference Paper November, 2020
Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory Conference Paper November, 2020
