TECHNOLOGY OF NON-PRODUCTION REACTOR FUELS REPROCESSING BUDGET ACTIVITY 2790 QUARTERLY REPORT

Technical Report · Thu May 19 04:00:00 EDT 1960

OSTI ID:4136159

Cooper, V R

Current planning calls for location of the receiving and storage, mechanical treatment, dissolution, clarification, and solution storage facilities at the Uranium Recovery Plant. Hachsaw testing was completed with final tests on the last three types of saws. scouting studies of the rankee fuel disassembly were made. A 304-L stainless steel shear blade faced with Stellite was tested. A cluster of 15, Zircaloy-clad, swaged UO/sub 2/ rods was sheared to study the dispersion of UO/sub 2/ fines in basin fluid. The Zirflex Precess, which employs aqueous NH/sub 4/F for dejacketing Zr-clad elements was studied to determine the solubility of both rr of U-Mo tures. - solution, the H/sub 2/ in the off- gas increases rapidly to about system devised. The corrosion of stainless steel, Monel, titanium, and tantalum by boiling decontaminating magents was studied. The study of the effect of geometrical shape on the dissolution rate of 2-S Al in Hg-catalyzed 5.6M HNO/sub 3/ at 80 to l00 deg C was completed. Studies of pulse column pressure transients were carried out to develop the causes of such transients observed in plant equipment. Pilot plant tests were made to determine if holding extraction column feed for periods of days prior to extraction adversely affects U recovery. The effectiveness of static pressure procees to indicate column flooding was evaluated. The development of an instrument to detact abnormal U concentrations in extraction raffinate streams is described. Service tests of modified camrned motor pusips were continued. A thermal flowmeter was tested, and a pulse amaplitude indicater devised. The binetics of Sr dissolution are being studied in mixtures of HNO/sub 3/ and HF. The ion exchange, solvent extraction, and precipitation of Zr from various media are described. Problems encountered in the operation of a small waste calciner for production of experimental quantities of high-activity calcined solids are described. Studies of Ru behavior in calcining included an evaluation of the effect of a nitric oxide atmosphere in suppressing volatility, distribution of Ru in the pilot plant off-gas system, amsorbents for Ru, and mercaptide precipitation. The effectiveness of a venturi scrubber for particle removal was also studied. Corrosion of heating surfaces and spray nozzles is reported, and data are given for the leaching of fission products from calcined alumina. Data for the B content of ingots used in ETR fuel element production were used to estimate the amount of B in selected elements. Statistical studies were made of the carminic acid method for B determination, the isotopic dilution method for U analysis, TBP determination by acid extraction, and experimental techniques for waste calcination and Zr extraction. Improvements in spectrophotometric methods for the determination of U were developed. (W.L.H.)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• NSA Number: NSA-14-016719
• OSTI ID: 4136159
• Report Number(s): HW-65267
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ALUMINUM
AMMONIUM COMPOUNDS
CANNING
CHEMISTRY
CHROMIUM ALLOYS
CORROSION
DISPERSIONS
FLUORIDES
FUEL ELEMENTS
FUELS
HYDROXIDES
IRON ALLOYS
MERCURY NITRATES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NITRIC ACID
PLANNING
RECOVERY
REPROCESSING
RODS
SAFETY
SOLUTIONS
STAINLESS STEELS
STORAGE
SULFEX PROCESS
TESTING
URANIUM
URANIUM ALLOYS
URANIUM DIOXIDE
ZIRCALOY
ZIRFLEX PROCESS 5