RESEARCH AND DEVELOPMENT ACTIVITIES. FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, January-March 1963

Technical Report · Mon Apr 01 00:00:00 EST 1963

OSTI ID:4713213

Irish, E.R. ed.

The radiant-heat spray calciner and pot calciner in the High-Level Radiochemistry Facility were used for additional experimental studies of full- level Purex 1 WW calcination. Two spray calcination runs and three pot calcination runs were made to produce calcined wastes of specific characteristics and to evaluate off-gas decontamination requirements The large Cold Semi-Works radiant-heat spray calciner was operated with the primar objective of testing draft tubes and their effectiveness in minimizing wall deposits of calcine. Additional data were obtained on reactor capacity, the effects of using steam as an atomizing gas, and the behavior of mercury compounds in the waste solution. Studies of the various parameters which control the behavior of the electrostatic bubble scrubber were undertaken. Development work on the storage of waste slurries included studies on suspension of slurries and removal of settled sludges in tanks. Engineering-scale studies of the packaging of radiocesium and radiostiontium concentrates were continued. Equilibrium constants were determined for 3 binary alkali metal cation systems on 7 zeolites. Irregularities in some isotherms can be accounted for on the basis of crystal stacking faults and ionic size. Two runs were made in the Micro Pilot Plant (MPP) with Purex Tank Farm condensate to evaluate the decontamination ability of thin precoat beds of cation exchangers and their beneficial application to an overall condensate decontamination flowsheet. Additional data were obtained for definition of the flowsheet for cesium recovery from Purex high-level wastes by use of inorganic ion exchangers. Data were obtained on the volatility and elution of cesium and strontium from loaded inorganic ion exchangers heated to 700 and 1000 C. Extensive laboratory and pilot plant development work was performed on the CSREX solvent extraction process for the simultaneous extraction of cesium, strontium and rare earths from Purex 1 WW. The solvent used in this new process is a combination of 0.3 M D2EHPA and 0.5 M BAMBP (di-2-ethylhexyl phosphoric acid and 4-secbutyl-2-STAk methylbenzyl!phenol) in Soltrol diluent. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-17-028581
• OSTI ID: 4713213
• Report Number(s): HW-77299
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-63
• Country of Publication: United States
• Language: English

Related Subjects

WASTE DISPOSAL AND PROCESSING
ADSORPTION
ALUMINUM SILICATES
ARYL RADICALS
BENZYL RADICALS
BUBBLES
BUTYL RADICALS
CESIUM 137
CHEMICAL REACTIONS
CRYSTALS
DECOMPOSITION
DECONTAMINATION
DEFECTS
DIAGRAMS
EFFICIENCY
ELECTROSTATICS
FISSION PRODUCTS
GASES
GRAIN SIZE
HEATING
HIGH TEMPERATURE
ION EXCHANGE MATERIALS
LEACHING
LIQUEFYING
MERCURY COMPOUNDS
METHYL RADICALS
PACKAGING
PHENOLS
PHOSPHORIC ACID
PUREX PROCESS
RARE EARTHS
REACTION KINETICS
RESIDUES
SLURRIES
SOLVENT EXTRACTION
SPUTTERING
STEAM
STORAGE
STRONTIUM 90
SUSPENSIONS
TUBES
VESSELS
VOLATILITY
WASTE PROCESSING
WASTE SOLUTIONS
ZEOLITES