RESEARCH AND DEVELOPMENT ACTIVITIES ON FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, April-June 1963

Technical Report · Mon Jul 01 00:00:00 EDT 1963

OSTI ID:4634965

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. A spray calcination run was made with ammonianeutralized waste for comparison with caustic-neutralized waste. Pot calcination runs were directed toward determining the effect of calcium on sulfate retention and fission product behavior and the effect of excess sodium nitrate on cesium loss and calcine stability. The large Cold Semiworks radiant- heat spray calciner was operated for further evaluation of the calciner capacity and filter system suitability. In addition, powders were produced for use in a corrosion study for the evaluation of calciner construction materials. Several scouting runs were made to evaluate the ability of the system for making phosphate glass. The parametric study of the electrostatic bubble scrubber was concluded. The status and schedule for the Waste Solidification Engineering Prototypes are discussed. A sugar denitration process for Purex 1 WW, as a substitute for the formaldehyde process, was developed through laboratory, hot- cell, and engineering-scale pilot plant studies and adopted for process testing in the plant. The zeolite Linde 13X was found to be cerium selective in the presence of alkali metal cations but not in the presence of alkaline earth cations. The kinetics of a replacement type reaction were examined experimentally and compared to a theoretical model developed by Crank. Binary ion exchange data were used to predict equilibrium distribution of cations between zeolites and solutions containing three or more exchangeable cations. Predicted values compared favorably with experimentally determined values. Ion exchange and sorption methods are being evaluated for removal of ruthenium from Purex acid recovery condensate. Experiments were continued in the Micro Pilot Plant with Purex Tank Farm condensate to evaluate the ability of thin precoat beds of an anion exchange resin for ruthenium decontamination. Additional data were obtained for definition of the flowsheet for cesium recovery from Redox high- level waste by use of Duolite C-3 resin. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-17-038578
• OSTI ID: 4634965
• Report Number(s): HW-78188
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-63
• Country of Publication: United States
• Language: English

Related Subjects

WASTE DISPOSAL AND PROCESSING
ACIDITY
ADSORPTION
ALDEHYDES
ALKALI METALS
BUBBLE CHAMBERS
CALCIUM
CATIONS
CERIUM
CESIUM
CHEMICAL REACTIONS
CORROSION
DECOMPOSITION
DECONTAMINATION
DENITRATION
DIAGRAMS
DISTRIBUTION
EFFICIENCY
ELECTROSTATICS
FILTERS
FORMIC ACID
GLASS
ION EXCHANGE
ION EXCHANGE MATERIALS
LABORATORY EQUIPMENT
LOSSES
MECHANICAL STRUCTURES
NITRIC ACID
PHOSPHORUS OXIDES
POWDERS
PUREX PROCESS
RADIOCHEMISTRY
REACTION KINETICS
REDOX PROCESS
REMOTE HANDLING
REPROCESSING
RUTHENIUM
SODIUM NITRATES
SOLVENT EXTRACTION
SPUTTERING
SUGARS
SULFATES
TESTING
VESSELS
WASTE SOLUTIONS
ZEOLITES