issuing from b the solvent 6 which was charged with 1 55 g l of uranium was treated in c with 40 l h of a recycled solution 7 of hf in a proportion of 12 by weight and containing 150 g l of uf 4 coming from d and after the addition of a make up amount at 10 of 70 by weight the emulsion 8 issuing from c was separated in d into a flow of organic solvent 3 which was recycled to the extraction step and a suspension of uf 4 in hf 9 a part of which was recycled to c while the other part 11 was subjected to a filtration operation in order to separate uf 4 from the mother liquors that procedure resulted in the recovery of 1200 g h of a product with a moisture content of 37 and 25 of uranium that is to be compared to a test which was carried out in accordance with the prior art using the same reactants the same ore and the same flow rates in this test it was found that on the one hand it was necessary to use a 15 solution of hf and a make up amount of solvent of 300 g h in order to provide an identical extraction yield and on the other hand the suspension 9 being unfilterable it was necessary to have recourse to centrifuging in order finally to obtain a product which still contained 55 moisture it is thus possible to see the advantages of the present process which can be applied to all problems in regard to recovery of uranium in the form of uf 4 from phosphate bearing solutions when there is a wish to reduce the period of contact between.