Transient Testing of Natural Circulation Flow in Cartridge Experiments Conference Paper November, 2020
Design Overview of the Facility to Alleviate Salt Technology Risks (FASTR) Conference Paper November, 2020
Initial Irradiation Tests on the TCR Fuel Form at MIT Nuclear Reactor Laboratory Conference Paper November, 2020
Microstructural characterization and assessment of mechanical properties of concrete based on combined elemental analysis techniques and Fast-Fourier transform-based simulations Journal October, 2020
Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions Journal October, 2020
Performance of U3Si2 in an LWR following a cladding breach during normal operation Journal October, 2020
Assessment of Near-Term Fuel Screening and Qualification Needs for Nuclear Thermal Propulsion Systems Journal October, 2020
