Process for the separation and recovery of molybdenum and uranium from leach solution using ion exchange

A process is described for recovering uranium from a pregnant lixiviant containing uranium values and a certain portion of molybdenum values comprising passing the pregnant lixiviant through an anion exchange resin to capture the uranium and molybdenum values on the resin, eluting the uranium and molybdenum values from the resin with a salt solution, passing the elute through a weak acid cationic resin in its hydrogen form to capture the uranium values on the resin and treating the resulting eluate to precipitate uranium therefrom to produce the familiar 'yellow-cake'