Removal of hazardous radionuclides from uranium ore and/or mill tailings. Progress report, October 1, 1978-September 30, 1979
The leaching of uranium ore and mill tailings to remove radium was studied. A few scouting tests were performed to obtain data on the recovery of radium, thorium, and uranium from leach liquors and on the recycle of leaching agents. Nitric acid, hydrochloric acid, ethylenediaminetetraacetic acid (EDTA), and diethylenetriaminepentaacetic acid (DTPA) were evaluated as leachants using one sample of a western US ore and two samples of tailings obtained from different uranium mills that employ the sulfuric acid leach process. Leached solids with radium contents approaching 10 pCi/g (98% radium removal) were obtained after six stages of batch, crosscurrent leaching with 3 M HNO/sub 3/ at 33% concentration of solids and a temperature of 60/sup 0/C. On the basis of two-stage tests on mill tailings, 0.5 M EDTA solutions at pH values of 8.2 to 11.6 were found to be more effective, while hydrochloric acid in two- or three-stage tests was less effective than nitric acid. Solutions of 0.3 M EDTA and 0.05 M DTPA were ineffective. No important differences were observed in the leaching behavior of ore and of mill tailings derived from the same ore. The residue remaining after six stages of nitric acid leaching was relatively intractable to radium leaching with water or additional nitric acid leaching. Tests indicated that the recycle of nitric acid is chemically feasible by evaporating the leach liquors to recover unused acid and then thermally decomposing the metal salts to recover consumed acid. Radium recoveries of 99+% by carrying on barium sulfate were shown to be chemically feasible in a series of experiments with leach liquors, but processing applications would probably require methods for barium recycle and barium-radium separation. Recovery of /sup 230/Th and uranium from nitrate leach liquors by tri-n-butyl phosphate extraction appears promising in initial tests.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5627444
- Report Number(s):
- ORNL/TM-7065; TRN: 80-004401
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
MILL TAILINGS
LEACHING
RADIOACTIVE WASTE MANAGEMENT
RADIUM
MATERIALS RECOVERY
THORIUM
URANIUM
URANIUM ORES
DTPA
EDTA
FEED MATERIALS PLANTS
HYDROCHLORIC ACID
NITRIC ACID
RADIOACTIVE WASTE PROCESSING
RECYCLING
SULFURIC ACID
ACTINIDES
ALKALINE EARTH METALS
AMINO ACIDS
CARBOXYLIC ACIDS
CHELATING AGENTS
DISSOLUTION
DRUGS
ELEMENTS
HYDROGEN COMPOUNDS
INDUSTRIAL PLANTS
INORGANIC ACIDS
MANAGEMENT
METALS
NUCLEAR FACILITIES
ORES
ORGANIC ACIDS
ORGANIC COMPOUNDS
PROCESSING
RADIOPROTECTIVE SUBSTANCES
RECOVERY
RESPONSE MODIFYING FACTORS
SEPARATION PROCESSES
SOLID WASTES
TAILINGS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing
050400 - Nuclear Fuels- Feed Processing