Chemical Engineering Division Fuel Cycle Programs. Quarterly progress report, January-March 1979
In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing of refractory metals and alloys, graphite, and SiC in PDPM environments was done. A tungsten-metallized Al/sub 2/O/sub 3/-3% Y/sub 2/O/sub 3/ crucible was successfully fabricated. Tungsten microstructure of a plasma-sprayed tungsten crucible was stabilized by nickel infiltration and heat treatment. Solubility measurements of Th in Cd and Cd-Mg alloys were continued, as were experiments to study the reduction of high-fired ThO/sub 2/. Work on the fused salt electrolysis of CaO also was continued. The method of coprocessing of U and Pu by a salt transport process was modified. Tungsten-coated molybdenum crucibles were fabricated. The proliferation resistance of chloride volatility processing of thorium-based fuels is being evaluated by studying the behavior of fission product elements during chlorination of U and Th. Thermodynamic analysis of the phase relationships in the U-Pu-Zn system was initiated. The Pyro-Civex reprocessing method is being reviewed. Reactivity of UO/sub 2/ and PuO/sub 2/ with molten equimolar NaNO/sub 3/-KNO/sub 3/ is being studied along with the behavior of selected fission product elements. Work was continued on the reprocessing of actinide oxides by extracting the actinides from a bismuth solution. Rate of dissolution of UO/sub 2/ microspheres in LiCl/AlCl/sub 3/ was measured. Nitriding rates of Th and U dissolved in molten tin were measured. In work on the encapsulation of radioactive waste in metal, leach rates of a simulated waste glass were studied. Rates of dissolution of metals (potential barrier materials) in aqueous media are being studied. In work on the transport properties of nuclear waste in geologic media, the adsorption of iodate by hematite as a function of pH and iodate concentration was measured. The migration behavior of cesium in limestone was studied in relation to the cesium concentration and pH of simulated groundwater solutions.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5034027
- Report Number(s):
- ANL-79-45
- Country of Publication:
- United States
- Language:
- English
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Chemical Engineering Division fuel cycle programs. Quarterly progress report, April-June 1979. [Pyrochemical/dry processing; waste encapsulation in metal; transport in geologic media]
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JULY, AUGUST, SEPTEMBER 1958
Related Subjects
CADMIUM
SOLUBILITY
CALCIUM OXIDES
ELECTROLYSIS
FUEL CYCLE
CHEMICAL REACTIONS
RESEARCH PROGRAMS
PLUTONIUM
PHASE STUDIES
PLUTONIUM DIOXIDE
POTASSIUM NITRATES
SODIUM NITRATES
THORIUM
TUNGSTEN
MICROSTRUCTURE
URANIUM
URANIUM DIOXIDE
DISSOLUTION
ZINC
CHLORIDE VOLATILITY PROCESS
MICROSPHERES
PYROCHEMICAL REPROCESSING
SPENT FUELS
THORIUM OXIDES
ACTINIDE COMPOUNDS
ACTINIDES
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
CALCIUM COMPOUNDS
CHALCOGENIDES
CRYSTAL STRUCTURE
ELEMENTS
ENERGY SOURCES
EXTRACTIVE METALLURGY
FUELS
LYSIS
MATERIALS
METALLURGY
METALS
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
POTASSIUM COMPOUNDS
PYROMETALLURGY
REACTOR MATERIALS
REFRACTORY METALS
REPROCESSING
SEPARATION PROCESSES
SODIUM COMPOUNDS
THORIUM COMPOUNDS
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
TRANSURANIUM ELEMENTS
URANIUM COMPOUNDS
URANIUM OXIDES
050800* - Nuclear Fuels- Spent Fuels Reprocessing