CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1960

Technical Report · Mon Oct 31 00:00:00 EST 1960

DOI:https://doi.org/10.2172/4163455· OSTI ID:4163455

Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg C has been in trouble-free operation for 3000 hrs. Recovery of Pu from Mg solution by distillation of Mg was demonstrated on 1-g Pu scale. The solubility of Th in liquid Cd was measured over the temperature range from 1.9 x 10/sup -3/ per cent at 348 deg C to 1.8 x 10/sup -2/ per cent at 658 deg C. The solubility of Mn in liquid Cd was found to range from 0.27% at 414 deg C to 1.43% at 661 deg C. The solubility of Ni in liquid Cd was measured. The partition of U between liquid Al and liquid Cd was studied as a function of U concentration. The reaction of Al with a liquid Cd solution containing U, Zr, and Ce was studied. The free energy of formation of the U--Pb intermetallic compound UPb/sup 3/ was measured between 374 and 846 deg C by means of a galvanic cell method. Magnetic susceptibility measurements on the intermetallic comPound CeCd/sub 11/ were made over a range of temperature from 4 to 295 deg K. Fuel Cycle Applications of Volatility and Fluidization Techniques. The Direct Fluorination Process is currently aimed toward the processing of the Zircaloyclad, UO/sub 2/ fuel typical of the Dresden Reactor. The direct fluorination of dense UO/sub 2/ pellets submerged in an inert fluidized medium was carried out in a 3-inch reactor at 500 deg C at fluorine concentrations up to 30%. Experimental work has continued to determine the mechanism of the nickel-- fluorine reaction. In the development of the ADF process, current emphasis is being directed toward recovery of U from low U--Zircaloy-2 fuel alloys. A series of four dissolutions was carried out semicontinuously in the graphite pilot plant dissolver according to the Fused Salt Fluoride Volatility Process flowsheet. Additional studies of the one-step fluid-bed process for the conversion of UF/sub 6/ to UO/sub 2/ with steam and hydrogen are reported. Reactor Safety. The oxidation, ignition, and combustion processes of U, Zr, Th, and Pu are being studied in order to provide information leading to an understanding of the reactions. Reactor Chemistry. Data are being obtained on the neutron capture cross sections of U/sup 236/ as a function of neutron energy. The Reactor Decontamination Program is directed principally to bciling water reactors. A stainless steel loop simulating the action of a boiling water reactor was operated with Y/sup 90/ and Cs/sup 137/ tracer activities. A program of research directed toward the selection and evaluation of materials for nuclear superheaters was initiated. (For preceding pericd see ANL-6101.) (W.L.H.)

• Research Organization: Argonne National Lab., Ill.
• DOE Contract Number: W-31-109-ENG-38
• NSA Number: NSA-14-021559
• OSTI ID: 4163455
• Report Number(s): ANL-6145
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

CHEMISTRY
ALUMINUM
CADMIUM
CADMIUM ALLOYS
CERIUM
CHEMICAL REACTIONS
CORROSION
DISTILLATION
FUELS
INTERMETALLIC COMPOUNDS
LEAD
LIQUID METALS
MAGNESIUM
MAGNESIUM ALLOYS
MANGANESE
MEASURED VALUES
METALLURGY
NICKEL
PLANNING
PLUTONIUM
RECOVERY
REDUCTION
REPROCESSING
SEPARATION PROCESSES
SOLUBILITY
SOLUTIONS
STAINLESS STEELS
SUSCEPTIBILITY
TEMPERATURE
THORIUM
URANIUM
URANIUM ALLOYS
URANIUM OXIDES
ZINC
ZIRCONIUM