In-pile experiments at reactor BOR-60 was shown an interaction between nitride fuel and stainless steel in the range of 8-11% burn up (HA). These are the most important factors that make uranium nitride an interesting candidate to replace oxide: higher fissile atom density enabling higher power density, and higher thermal conductivity resulting in safer operation due to reduction in operating central line temperature. @article{osti_4324037, title = {Uranium nitride fuel development, SNAP-50}, author = {DeCrescente, M A and Freed, M S and Caplow, S D}, abstractNote = {Declassified 12 Sep 1973. @article{osti_1606770, title = {Uranium nitride tristructural-isotropic fuel particle}, author = {Terrani, Kurt and Jolly, Brian C. and Harp, Jason}, abstractNote = {A summary of activities around concept development, design, manufacturing, and early irradiation testing of a novel coated fuel particle, uranium nitride tristructural-isotropic fuel is provided. Uranium nitride powder was prepared from uranium metal via hydride and higher nitride. SCC says tests confirm serviceability of uranium-plutonium nitride fuel 18 November 2020 . uranium nitride fuels;nuclear ceramic materials;uranium mononitride;thermal conductivity;direct reaction Do you want to read the rest of this chapter? Print Email . "Nitride fuels are also well suited to future Generation IV nuclear power systems, which focus on safety, and feature a sustainable closed reactor fuel cycle. The pellets are 6.9 mm in diameter and 7 mm long, and are of natural and 5% enriched uranium. (Youinou & Sen, 2014) and uranium-nitride fuel (Y. Arai, 2012) , which is stud ied in the present work. Request full-text Comparison of uranium plutonium nitride and thorium nitride fuel for 500 MWth gas‐cooled fast reactor has been done. Gas‐cooled fast reactor is one type of generation IV reactor that can be operated in high temperature. Uranium nitride is most popular nuclear fuel for Fast Breeder Reactor New Generation. Russia’s Siberian Chemical Combine (SCC - part of Rosatom’s TVEL Fuel Company) said that it had produced more than 1000 experimental fuel elements based on mixed uranium-plutonium nitride fuel (MNUP fuel) during its eight years of participation in the Proryv (Breakthrough) project. Due to the high temperature, it can be used in hydrogen production. Uranium nitride and uranium carbonitride fuel pellets were prepared for irradiation in the Japan Material Testing Reactor.