CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION B MONTHLY PROGRESS REPORT, JANUARY 1960

Technical Report · Mon Apr 11 00:00:00 EST 1960

OSTI ID:4089357

Blanco, R E

The solubility of zirconium fluoride in HNO/sub 3/-NH/sub 4/F solutions was determined at 25 deg C. The solubility of MoO/sub 3/- 2H/sub 2/O in 2 to 5M HNO/sub 3/ at 26 deg C decreased with increasing uranyl nitrate concentration. Dissolution rates of 95% ThO/sub 2/-5% UO2 pellets decreased as the pellet density increased. It was determined that the gas evolved during the Zirflex Process was I% H/sub 2/, 0.3% O/sub 2/, 0.2% N/sub 2/, and the>i>s rest NH/sub 3/. Uranium recovery from graphitized fuel specimens containing 0.7 and 5% uranium was accomplished by grinding and leaching with HNO/sub 3/. In the Zirflex Process, hot-cell experiments showed soluble plutonium and uranium losses to the declad solution of 0.05 to 0.08 and 0.01 to 0.11%, respectively. In dissolution of stainless-steel-clad UO/sub 2/ pellets by the Darex-Purex Process, uranium losses were less than 0.02% per cycle. Boildown curves for thorium nitrate- nitric acid solutions demonstrate that regardless of original composition the acid is not completely removed until the thorium is concentrated to about 1300 g/ l. Corrosion studies were made on Ni-o-nel, Hastelloy F, and stainless steel in the Zirflex Process, on titanium in Thorex dissolver solutions, and on stainless steel in the Darex-Purex Process. Solubilities of uranyl dibutyl phosphate in HNO/sub 3/ and 30% TBP-Amsco-HNO/sub 3/ solutions were determined. Solvesso-100 was found to reduce radiation damage when used in place of Amsco 125-82 in TBP solutions. Addition of calcium as hydroxide or colloidal silicate to synthetic Purex 1WW waste prevented volatilization of sulfate. Greater than 99% of the cesium and strontium was removed from 667 volumes of low-level process water waste by passage through one volume of sodium-form Duolite C-3. The degree of ionization and total enthalpy of hydrogen and argon plasmas at one atmosphere were calculated for temperatures up to 20,000 deg K. (For preceding period see CF- 59-12-74.) (M.C.G.)

• Research Organization: Oak Ridge National Lab., Tenn.
• NSA Number: NSA-15-011039
• OSTI ID: 4089357
• Report Number(s): CF-60-2-11
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

CHEMISTRY
AMMONIA
AMMONIUM COMPOUNDS
AMSCO
ARGON
BUTYL PHOSPHATES
CALCIUM HYDROXIDES
CESIUM
CHROMIUM ALLOYS
COPPER ALLOYS
CORROSION
DAREX PROCESS
DENSITY
ENTHALPY
FLUORIDES
FUELS
GRAPHITE
HASTELLOY
HYDROGEN
ION EXCHANGE MATERIALS
IONIZATION
KEROSENE
LEACHING
MOLYBDENUM ALLOYS
MOLYBDENUM OXIDES
NI-O-NEL
NICKEL ALLOYS
NITRIC ACID
NITROGEN
OXYGEN
PELLETS
PLASMA
PLUTONIUM
PUREX PROCESS
QUANTITATIVE ANALYSIS
RECOVERY
REPROCESSING
RESIDUES
RESINS
SILICATES
SOLUTIONS
SOLVENT EXTRACTION
SOLVENTS
SOLVESSO
STAINLESS STEELS
STRONTIUM
SULFATES
THERMODYNAMICS
THOREX PROCESS
THORIUM NITRATES
THORIUM OXIDES
TITANIUM