Some Aspects of the use of ZrN as an Inert Matrix for Actinide Fuels
The sodium compatibility and the nitric acid dissolution of (Zr(0.80)U(0.20)N, prepared by carbothermic reduction of the oxide, were determined. No interaction with liquid sodium (T=823 K) was observed. The material readily dissolved in nitric acid (T=378-383 K). From these results it is concluded that ZrN is an attractive inert matrix in fast reactor fuels for the incineration of plutonium and minor actinides.
Bibliographic Reference: An article published in: Journal of Nuclear Materials 288(2001) pp.233-236
Record Number: 200013392 / Last updated on: 2001-06-27
Original language: en
Available languages: en