CHEMICAL TECHNOLOGY DIVISION, UNIT OPERATIONS SECTION MONTHLY PROGRESS REPORT FOR NOVEMBER 1959
A steady state, uranyl nitrate concentration profile was established across a water-TBP interface and was analyzed by means of photographic photometry. Survey of the literatare indicated that H/sub 2/ and CO in the helium coolant of the gas-cooled reactor may be oxidized to CO/sub 2/ and H/sub 2/O in a bed of mixed copper oxides at bed temperatures between 1000 and 1200 ction prod- F with less than 1 ppm O/sub 2/ in the effluent gas. Classification of the 38 pounds of 2 mu flame calcined thoria was completed. Studies of uranium loading rate on sulfateequilibrated 1200 mu Dowex 21K from average sulfate solutions continued to give apparent uranium diffusion coefficients of approximately 1.3 x 10/sup -7/ sq cm/sec for sulfate concentration up to 0.30 M. In the Thorex core dissolution of unirradiated Consolidated Edison fuel pellets (UO/sub 2/ThO/sub 2/ , 96%) using a flooded pot recycle technique (dissolver product is continuously combined with feed dis solvent), approximately 90% of the pellets was dissolved in 8 hrs. The results of 13 semi-continuous Sulfex dissolutions of 304L stainless steel with boiling 6 M H/sub 2/SO/sub 4/ and 4 M H/sub 2/SO/sub 4/ showed that the reaction rates and product solution loadings were 15 to 18% and 12% higher, respectively, for the 4 M acid for the same ratios of dissolvent flow rate to initial surface area. Centrifugation tests of Sulfex declad liquors produced centrifuge cakes averaging 0.5 volume % of the initial volume. In a single batch leaching of 3.9 kg of U as unnirradiated UO/sub 2/ from 0.4-in. diameter stainless steel jacketed tubular fuel in boiling 13 M HNO/sub 3/, the uranium was dissolved in approximately 35 minutes at an average rate of 0.044 g/ min-g of U initially present. Work was started to evaluate the now capacity and stage efficiency of pulse columns as a function of operating variables and cartridge design for application to reprocessing power reactor fuels. A study of the sorption of UF/sub 6/ from a stream diluted by a gas inert to NaF has been undertaken to provide data for careful design of sorption systems. Initial tests with the 8-in. diam by 78-in. long pot calciner under conditions of maximum feed rate indicated the need for additional de-entrainment within the pot to prevent solids buildup in the off-gas line. (For preceding period see CF-59-10-77.) (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- NSA Number:
- NSA-14-010520
- OSTI ID:
- 4187578
- Report Number(s):
- CF-59-11-54
- 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 October 1959
Related Subjects
ADSORPTION
BUTYL PHOSPHATES
CARBON DIOXIDE
CARBON MONOXIDE
CENTRIFUGATION
COOLANTS
COPPER OXIDES
EXTRACTION COLUMNS
FUELS
GASES
HELIUM
HYDROGEN
LEACHING
MIXING
NITRIC ACID
OXYGEN
PELLETS
PHOTOGRAPHY
PHOTOMETRY
PULSE COLUMNS
PULSES
REACTOR CORE
REACTOR FUELING
REACTORS
REPROCESSING
RESINS
SODIUM FLUORIDES
SOLVENT EXTRACTION
STAINLESS STEELS
SULFATES
SULFURIC ACID
SURFACES
TEMPERATURE
THOREX PROCESS
THORIUM OXIDES
URANIUM
URANIUM HEXAFLUORIDE
URANYL NITRATES
WATER