Review and preliminary investigation into fuel loss from cermets composed of uranium nitride and a molybdenum-tungsten alloy for nuclear thermal propulsion using …
A ceramic–metal composite (cermet) of uranium nitride (UN) particles embedded in a
tungsten-molybdenum (W/Mo) alloy matrix is being considered as reactor fuel for nuclear …
tungsten-molybdenum (W/Mo) alloy matrix is being considered as reactor fuel for nuclear …
Nuclear thermal propulsion–Progress and potential
D Thomas - Journal of Space Safety Engineering, 2024 - Elsevier
This paper describes the current research and development efforts currently underway
within the United States on Nuclear Thermal Propulsion (NTP), with a particular focus on the …
within the United States on Nuclear Thermal Propulsion (NTP), with a particular focus on the …
A Study of a Surrogate Nuclear Thermal Propulsion Fuel Element
DS Tucker, AS Preston, ND Jerred… - Journal of Ceramic …, 2023 - osti.gov
We report a surrogate fuel, Zirconium Carbide/Titanium Nitride has been prepared using a
simple method to obtain a more uniform distribution of titanium nitride in the zirconium …
simple method to obtain a more uniform distribution of titanium nitride in the zirconium …