CHEMICAL TECHNOLOGY DIVISION, UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT FOR MARCH 1959
In a preliminary experiment, the integral diffusivity of 1 M FeCl/sub 3/ solution varied uniformly with the fraction difiused: from 0.3 x 10/sup -6/ cm/ sup 2//sec for 10 per cent diffused to 0.8 x 10/sup -6/ for 30 per cent diffused. A short Fluorox run made with crude UF/sub 4/ in the 4-in. fluidized bed showed that UF/sub 6/ could be produced from the impure feed. Denitration of Th(NO/sub 3/)/sub 4/ solutions on fluidized or mechanically agitated beds of ThO/sub 2/ and gave fine ThO/sub 2/ particles for all conditions tested. The rate of sorption of uranium into 40 micron Dowex 21K resin particles from a 0.0042 M uranyl sulfate solution was studied by measuring the uranium loading on individual beads as a function of time. Chloride concentrations of 28 to 51 ppm were produced in the solvent extraction feeds during five feed adjustment runs made with the Darex Reference flowsheet. Decladding of SS-clad /sub 4/ gave essentially identical results as batch decladding. When a Mark I prototype assembly was sheared into 0.75-in. lengths with a"plane of contact" blade in the 126-ton Manco shear, 22.2 g of metal fines (304L stainless steel) 1680 microns or less in size was produced with 36.5% less than 150 micron. UO/sub 2/ leached from sheared stainless steel cladding, 0.4 in. O.D. x 2.75-0.5 in. long, with 10 M HNO/sub 3/ at an average rate of 0.009 to 0.067 g/min/g of initial UO/sub 2/, respectively, and at initial rates of 0.052 to 0.29 g/ min/g. After four runs at approximately 700 ction prod- C with NaFLiF melts (initial concentration: 43 mol per cent NaF, final concentration approximately 12 mol per cent ZrF/sub 4/), average corrosion rates varied from 0.25 mils/hr maximum (at the interface) to 0.12 mils/hr minimum (in the vapor space). Heat transfer calculations on the storage of cylindrical containers of waste showed that the allowable specific heat generation in the waste can be increased by 20 to 30% by storage of the waste in air cooled vaults rather than burial with a 1-in. air gap between the container and the ground media. (For preceding period see CF-59-2-45.) (auth)
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- NSA Number:
- NSA-14-010511
- OSTI ID:
- 4187841
- Report Number(s):
- CF-59-3-61
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
Similar Records
CHEMICAL TECHNOLOGY DIVISION, UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT FOR MAY 1959
CHEMICAL TECHNOLOGY DIVISION, UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT FOR FEBRUARY 1959
Related Subjects
ADSORPTION
AIR
CHLORIDES
COOLING
CORROSION
CYLINDERS
DAREX PROCESS
DIFFUSION
FLUIDIZATION
FLUOROX PROCESS
HEAT TRANSFER
IRON CHLORIDES
LEACHING
LITHIUM FLUORIDES
MEASURED VALUES
MELTING
NITRIC ACID
PELLETS
PRODUCTION
REACTOR FUELING
REPROCESSING
RESINS
SAND
SODIUM FLUORIDES
SOLUTIONS
SOLVENT EXTRACTION
STAINLESS STEELS
STORAGE
SULFATES
SULFURIC ACID
THORIUM NITRATES
THORIUM OXIDES
URANIUM
URANIUM DIOXIDE
URANIUM HEXAFLUORIDE
URANIUM TETRAFLUORIDE
URANYL COMPOUNDS
VESSELS
WASTE SOLUTIONS
ZIRCONIUM FLUORIDES