QUARTERLY REPORT ON TECHNOLOGY OF NON-PRODUCTION REACTOR FUELS REPROCESSING BUDGET ACTIVITY 2790
Current processing concepts were reviewed at an AEC symposium during the period; a report of the sympesium is scheduled (TID-7513). Saw studies during the period included coldsaw and hacksaw testing. Preliminary conclusions are listed. Results of Yankee fuel element disassembly scouting experiments are presented along with those for shear basin studies to determine the UO/sub 2/ contamination in water. Development of the Zinflex Process is essentially complete. Studies on solution stability and effects of Na ion in Zirflex solutions are discussed along with methods of reducing U loss and results of pilot plant studies. In Sulfex Process development, depassivation studies were continued on 304-L stainless steel. No chemical agents were found to activate passive surfaces in 4 M H/sub 2/SO/sub 4/; however, coupling this alloy to carbon steel, Hastelloy F, or Ni-o-nel produced depassivation. Pilot plant and bench- scale dissolution studies using 304-L and 347 stainless steel in various H/sub 2/ SO/sub 4/ concentrations are reported. Core dissolution studies were continued with U--Mo alloys. Various ions were tested for their ability to complex molybdate ion formed during HNO/sub 3/ dissolution. Other experiments using 12 to 15 M HNO/sub 3/ on Al--Mo-- U alloys are also reported. Experiments on recirculating dissclvers with reservoirs are reperted. Highest dissolution rates were obtained using a well agitated dissolver and plug-flow reservoir. Continued development of the vertical tube and flooded tray dissolvers is reported. Experiments to determine the effects of an additional column on a common reservoir dissolver indicated that the tubes did not affect each other. Corrosion testing of construction materials such as Ni-o-nel, Hastelloy F, and 304-L stainless steel in various process acid and salt solutions was continued. Analysis of data from precision level experiments was completed and accuracy estimates are tabulated for the case of a storage tank. The determination of criticality parameters for 3% enriched U applicable to nuclear safety in reactor fuel reprocessing was continued. Data on critical mass and buckling and exponential measurements on 0.175 in. diameter heterogeneous rods are tabulated. Preliminary results of similar experiments with homogeneous systems are also given. (For preceding period see HW-62063.) (J.R.D.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-14-009548
- OSTI ID:
- 4174348
- Report Number(s):
- HW-63406
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALLOYS
CARBON STEELS
CHEMISTRY
CHROMIUM ALLOYS
CONTAMINATION
COPPER ALLOYS
CORROSION
CRITICALITY
ENRICHMENT
FUEL ELEMENTS
FUELS
HASTELLOY
MEASURED VALUES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NITRIC ACID
QUANTITATIVE ANALYSIS
REPROCESSING
RODS
SAFETY
SALTS
SOLUTIONS
STAINLESS STEELS
STORAGE
SULFEX PROCESS
SULFURIC ACID
SURFACES
TESTING
TITANIUM ALLOYS
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
WATER
YAEC
ZIRFLEX PROCESS