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
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions Journal October, 2020
Analysis of Fission Product Distribution and Composition in the TRISO Layers of AGR-2 Fuel Journal August, 2020
Evaluation of the Effects of Neutron Irradiation on First-Generation Corrosion Mitigation Coatings on SiC for Accident-Tolerant Fuel Cladding Journal August, 2020
