Ore dressing investigations have shown that the branerite/absite fractions of Crocker Well ore can be concentrated with reasonable recovery by flotation (G.D. Sheridan, R.D.-80, 1958). Although the separation from the acid consuming mica minerals...
Ore dressing investigations have shown that the branerite/absite fractions of Crocker Well ore can be concentrated with reasonable recovery by flotation (G.D. Sheridan, R.D.-80, 1958). Although the separation from the acid consuming mica minerals was good, separation from apatite could not be achieved. Laboratory work has shown that Crocker Well concentrates could be treated for recovery of uranium by admixture with Radium Hill concentrates and treated by a process similar to that used at Port Pirie (Moyle and Lawrie R.D.-49). Investigations have also shown that both the uranium and thorium can be recovered from leach liquors of Crocker Well concentrates using solvent extraction (Madigan R.D.-65, Part 1 and 2, 1958). To conclude the work it was decided that the latter proposal should be examined at pilot scale. The investigation lost most of its urgency and was carried out on an intermittent basis by the former R. and D. Branch of the Mines Department and later by AMDL. However in view of the very difficult problems involved in the separation of the leach residue and the lack of any real incentive in terms of using the material, the investigation has been discontinued without actually taking the investigation to a pilot plant operating on a continuous basis. An investigation has been conducted into the leaching of Crocker Well concentrates and the recovery of uranium and thorium from the leach liquor. Approximately 90% of the uranium and 80% of the thorium can be extracted from the concentrates by hot leaching using 1500 pounds of sulphuric acid per long ton of concentrates. Experimental shake-out tests on liquor from this material confirms the previous findings that the uranium and thorium can be recovered by solvent extraction using Alamine 336 or Tri-iso-octyl-amine for uranium and E.H.P.A. for thorium. Mixer settlers would be recommended for both operations based on previous experience with this equipment. Experiments with a rotating disc contactor showed that this type of equipment could not be recommended for this operation. The separation and recovery of leach liquor from residues has been shown to be quite difficult. Unless a satisfactory “extraction from pulp” process was developed the possibility of economic treatment of the concentrates is doubtful except by mixing with Radium Hill concentrates as previously suggested. In this case the thorium concentration of the liquors would be more dilute and its extraction of doubtful economic advantage.
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