Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, April-June 1978. [Advanced solvent extraction; accidents; pyrochemical; radwaste in metal matrix; waste migration]
Fuel cycle studies reported include development of centrifugal contactors for Purex processes. Tricaprylmethyl-ammonium nitrate and di-n-amyl-n-amylphosphonate are being evaluated as Thorex extractants. Dispersion of uranium and plutonium by fires, and mechanisms for subdividing and dispersing liquids and solids were reviewed. In the pyrochemical and dry processing program, a facility for testing containment materials is under construction; a flowsheet for carbide fuel processing has been designed and studies of carbide reactions in bismuth are underway; salt transport processes are being studied; process-size refractory metal vessels are being fabricated; the feasibility of AIROX reprocessing is being determined; the solubility of UO/sub 2/, UO/sub 2/ + fission products, and PuO/sub 2/ in molten alkali metal nitrates, has been investigated; a flowsheet was developed for reprocessing actinide oxides in molten salts; preparation of Th-U carbide from the oxide is being studied; new flowsheets based on the Dow Aluminum Pyrometallurgical process for reprocessing of spent uranium metal fuel have been prepared; the chloride volitility processing of thorium-based fuels is being studied; the reprocessing of (Th,U)O/sub 2/ solid solution in KCl-LiCl-ThCl/sub 4/-Th is being studied; and a flowsheet for processing spent nuclear fuel in molten tin has been constructed. Leach rates of simulated encapsulated waste forms in a metal matrix were studied. Nine criteria for handling waste cladding hulls were established. Strontium and tin migration in glauconite columns was measured. Radioactive Sr in a stream of water moved through oolitic limestone as rapidly as water, but in a stream of water equilibrated with the limestone, Sr moved through the limestone one-tenth as fast. Migration of trace quantities of Cs and I through kaolinite was studied. 88 figures, 53 tables.
- Research Organization:
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5748651
- Report Number(s):
- ANL-78-76
- Country of Publication:
- United States
- Language:
- English
Similar Records
Chemical Engineering Division fuel cycle programs. Quarterly progress report, July-September 1978
Chemical Engineering Division fuel cycle programs. Progress report, January--March 1978
Related Subjects
052002 -- Nuclear Fuels-- Waste Disposal & Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACCIDENTS
AEROSOLS
ALKALINE EARTH METALS
CARBONATE ROCKS
CENTRIFUGES
COLLOIDS
CONCENTRATORS
DISPERSIONS
DISSOLUTION
ELEMENTS
ENCAPSULATION
ENVIRONMENTAL IMPACTS
ENVIRONMENTAL TRANSPORT
EXTRACTION APPARATUSES
FIRES
FUEL CANS
FUEL CYCLE
FUEL REPROCESSING PLANTS
LEACHING
LIMESTONE
MANAGEMENT
MASS TRANSFER
METALS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
PROCESSING
PUREX PROCESS
RADIOACTIVE WASTE PROCESSING
RADIONUCLIDE MIGRATION
REPROCESSING
RESEARCH PROGRAMS
RESERVOIR ROCK
ROCKS
SEDIMENTARY ROCKS
SEPARATION PROCESSES
SILICATES
SILICON COMPOUNDS
SOLS
SOLVENTS
STRONTIUM
THOREX PROCESS
TIN
WASTE MANAGEMENT
WASTE PROCESSING