Thermal conductivity of gadolinium added uranium mononitride fuel pellets sintered by spark plasma sintering

Simulation of uranium mononitride spent fuel: A crystallographic approach

“…Dissociation of UN was observed to start even at 1500°С, Inoyue & Leitnaker (1968) [9]. Uranium mononitride is considered superior because of its high fissionable density (see Hayes et al (1990) [10]), a thermal conductivity 4-8 times higher than UO 2 , as reported by Kim & Ahn (2021) [11], resulting in a lower thermal gradient in the fuel sections and less irradiation induced restructuring, revealing consequently low fission gas releases and low reactivity with cladding materials. Although fuel swelling is slightly higher than for UO 2 , the combined mechanical, thermal (see Takahashi et al (1971) [12]) and radiation stability (see Martin et al (1965) [13]) of UN makes it a promising alternative to conventional oxide fuel.…”