QUARTERLY REPORT ON TECHNOLOGY OF NON-PRODUCTION REACTOR FUELS REPROCESSING BUDGET ACTIVITY 2790
Current plans for location of the receiving and storage, mechanical treatment, dissolution, clarification, and solution storage at the uranium recovery plant are described. Underwater shearing studies conducted using stainless steel-clad swaged UO/sub 2 fuels to determine the characteristics of the UO/sub 2/- water suspension formed during shearing showed that about 3% U may be suspended during normal operation. In life tests, a cold saw was used to cut about the equivalent of the presently scheduled annual processing load of stainless steel without significant blade wear. Optimization of the Zirflex Process to reduce U loss is discussed. Assuming formation of U(IV) in cooled cladding waste at a rate of 10/sup -3/ moles/(l)(hr) (about ten times greater than is expected from radiolysis), a concentration of 0.01 M hyposulfite at pH 8 would hold the U(VI) concentration to about 1.7 x 10/sup -3/ M. Data on Zr dissolution vs. electrical conductivity are presented. Effects of nitrate ions in stainless steel dissolution were studied. It was found that the concentration should not be more than 0.01 M during Sulfex stainless decladding operation. Electrolytic depassivation of stainless steel in sulfuric acid is reported. Evaluation of data from the first series of pilot plant runs involving the dissolution of 304-L stainless by the Sulfex Process indicates that the quantity of hydrogen observed in the off-gas was somewhat lower than stoichiometric quantities. Studies of foam formation in Zinflex and Sulfex Processes are discussed and observations on U--Mo alloy core dissolution are presented along with data on Na--HNO/sub 3/ reaction pressures. Darex pilot plant studies on stainless steel clad U core fuel elements were continued. New data on the role of the ferric ion in the Darex Process for dissolution of U--Mo alloys are given. In dissolver studies, dissolution of Hanford slugs in the vertical tube dissolver was initiated and data on dissolution of these slugs in the flooded tray dissolver are tabulated. Observations from corrosion studies of 304-L stainless steel, Hastelloy F, and Ni-o-nel by Zinflex and Sulfex solutions under recirculating dissolver conditions are discussed. In studies of first and second cycle Redox solvent extraction conditions using U-Mo alloy, gross beta and gamma decontamination factors through 2 cycles were 1/2 and 1/4, respectively, of those obtained in a control run employing an acid-deficient flowsheet. Development of a boron monitor was completed. Determination of criticality parameters for 3% enriched U applicable to nuclear safety in reprocessing fuels was continued. Exponential and critical approach measurements were conducted with 0.3 and 0.6 in. diameter enriched rods. A summary of extrapolation length and buckling data is presented. (For preceding period see HW-60298.) (J.R.D.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-14-009546
- OSTI ID:
- 4189099
- Report Number(s):
- HW-62063
- Country of Publication:
- United States
- Language:
- English
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TECHNOLOGY OF NON-PRODUCTION REACTOR FUELS REPROCESSING BUDGET ACTIVITY 2790. Quarterly Report
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BUCKLING
CANNING
CHEMISTRY
CHROMIUM ALLOYS
COPPER ALLOYS
CORROSION
CRITICALITY
DAREX PROCESS
DECOMPOSITION
DECONTAMINATION
ELECTRIC CONDUCTIVITY
ELECTROLYSIS
ENRICHMENT
FOAMS
FUEL CANS
FUEL ELEMENTS
FUELS
HASTELLOY
HYDROGEN
IONS
IRON
MEASURED VALUES
MOLYBDENUM ALLOYS
MONITORING
NICKEL ALLOYS
NITRATES
NITRIC ACID
NUMERICALS
RADIATIONS
REACTOR CORE
RECOVERY
REPROCESSING
RODS
SEPARATION PROCESSES
SODIUM
SOLUBILITY
SOLVENT EXTRACTION
STAINLESS STEELS
STORAGE
SULFEX PROCESS
SULFITES
SULFURIC ACID
SUSPENSIONS
TITANIUM ALLOYS
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
WASTE SOLUTIONS
WATER
ZIRCONIUM
ZIRFLEX