In situ carbonate leaching and recovery of uranium from ore depo

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

Patent

Rate now

  [ 0.00 ] – not rated yet Voters 0   Comments 0

Details

75103, 299 4, 299 5, 423 15, 423 17, C01G 4300

Patent

active

041559827

ABSTRACT:
Uranium ore deposits which contain certain proportions of other metals and elemental components, such as are present in redox roll front ore deposits, are selectively leached in situ by passing therethrough relatively dilute aqueous leach solutions comprising essentially from about 0.5 to 5 grams per liter of ammonium bicarbonate and from about 0.1 to 3 grams per liter of peroxide, preferably introduced as aqueous H.sub.2 O.sub.2, and sufficient ammonia to bring the solution to a pH of from about 7.4 to 9, and preferably from 7.5 to 8.5, thereafter withdrawing from the ore deposit the aqueous leach solution enriched in uranium which it preferentially extracts along with a generally lower proportion of other metals and elements as compared to their respective ratios in the ore deposit, and contacting the enriched leach solution with a strong base anion exchange material to strip the uranium from the leach solution. The uranium is eluted by treating the base anion exchange material with an aqueous eluant, and finally the uranium is recovered from the uraniferous eluate by first acidifying it and then treating with ammonia to produce a precipitate of relatively pure ammonium diuranate. The stripped leach solution is separated from the base anion exchange material and the stripped leach solution is recirculated through the ore deposit after adjusting it with more ammonium bicarbonate, peroxide and ammonia. After the uranium in the ore deposit is removed to the extent economically practicable, the leach solution is replaced with an aqueous reducing solution which is passed into the ore deposit in order to precipitate and render insoluble any uranium and elements such as vanadium, molybdenum and selenium. The process produces above ground a very low volume of impurities and waste solutions requiring disposal, and causes no significant or material contamination or deterioration of the underground deposits or any aquifer associated therewith.

REFERENCES:
patent: 2770520 (1956-11-01), Long et al.
patent: 2813003 (1957-11-01), Thunaes et al.
patent: 2896930 (1959-07-01), Menke
patent: 2964380 (1960-12-01), Kolodney et al.
patent: 2982602 (1961-05-01), Sherk et al.
patent: 3174821 (1965-03-01), Opratko et al.
patent: 3239306 (1966-03-01), Reusser et al.
patent: 3708206 (1973-01-01), Hard et al.
patent: 3792903 (1974-02-01), Rhoades
patent: 3860289 (1975-01-01), Learmont
Proceedings of the Second United Nations International Conference on The Peaceful Uses of Atomic Energy, vol. 3, "Processing of Raw Materials", pp. 333-339 and 444 (1958), United Nations, Geneva.

LandOfFree

Say what you really think

Search LandOfFree.com for the USA inventors and patents. Rate them and share your experience with other people.

Rating

In situ carbonate leaching and recovery of uranium from ore depo does not yet have a rating. At this time, there are no reviews or comments for this patent.

If you have personal experience with In situ carbonate leaching and recovery of uranium from ore depo, we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and In situ carbonate leaching and recovery of uranium from ore depo will most certainly appreciate the feedback.

Rate now

     

Profile ID: LFUS-PAI-O-1040502

  Search
All data on this website is collected from public sources. Our data reflects the most accurate information available at the time of publication.