Dissolution of mixed oxide fuel as a function of fabrication variables

Dissolution properties of mechanically blended mixed oxide fuel were very dependent on the six fuel fabrication variables studied. Fuel sintering temperature, source of PuO/sub 2/ and PuO/sub 2/ content of the fuel had major effects: (1) as the sintering temperature was increased from 1400 to 1700/sup 0/C, pellet dissolution was more complete; (2) pellets made from burned metal derived PuO/sub 2/ were more completely dissolved than pellets made from calcined nitrate derived PuO/sub 2/ which in turn were more completely dissolved than pellets made from calcined nitrate derived PuO/sub 2/; (3) as the PuO/sub 2/ content decreased from 25 to 15 wt % PuO/sub 2/, pellet dissolution was more complete. Preferential dissolution of uranium occurred in all the mechanically blended mixed oxide. Unirradiated mixed oxide fuel pellets made by the Sol Gel process were generally quite soluble in nitric acid. Unirradiated mixed oxide fuel pellets made by the coprecipitation process dissolved completely and rapidly in nitric acid. Fuel made by the coprecipitation process was more completely dissolved than fuel made by the Sol Gel process which, in turn, was more completely dissolved than fuel made by mechanically blending UO/sub 2/ and PuO/sub 2/ as shown below. Addition of uncomplexed fluoride to nitric acid during fuel dissolution generally rendered all fuel samples completely dissolvable. In boiling 12M nitric acid, 95 to 99% of the plutonium which was going to dissolve did so in the first hour. Irradiated mechanically blended mixed oxide fuel with known fuel fabrication conditions was also subjected to fuel dissolution tests. While irradiation was shown to increase completeness of plutonium dissolution, poor dissolubility due to adverse fabrication conditions (e.g., low sintering temperature) remained after irradiation.