Investigation of the operational limits of uranium-plutonium nitride fuels
The behaviour of uranium-plutonium nitride fuel in a thermal gradient, prepared by the carbothermic reduction process in a nitrogen atmosphere, has been investigated. Pellets with about 20% porosity, containing different amounts of oxygen impurity, fractured during the rise in temperature, but their structure and composition were stable up to about 2000 K. Strong restructuring, plutonium depletion and pellet collapsing occurred at higher temperatures. Oxynitride type inclusions in nitride fuel, containing more than 1500 ppm oxygen, melted at about 2600 K.
Bibliographic Reference: Article: Journal of Nuclear Materials, Vol. 184 (1991) pp. 167-176
Record Number: 199210091 / Last updated on: 1994-12-02
Original language: en
Available languages: en