RESEARCH AND DEVELOPMENT ACTIVITIES FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, July-September 1963

Technical Report · Tue Oct 01 00:00:00 EDT 1963

DOI:https://doi.org/10.2172/4122528· OSTI ID:4122528

Irish, E.R. ed.

The radiant-heat spray calciner in the High-Level Radiochemistry Facility was used for additional experimental studies of full-level Purex 1WW calcination. The unit was operated with ammonia-neutralized Purex waste plus sugar, acidic Purex waste with phosphate added, and with sugar added. Behavior of ruthenium and properties of the melt were observed. A tracer I/sup 131/ run was made in the 8inch diameter cold calciner to evaluate iodine behavior during calcination. The large Cold Semiworks spray calciner was operated for further evaluation of the calciner capacity and heat-transfer characteristics. Development of glass processes was initiated with installation and operation of a continuous melter for calcine powder. n elaboration on the sugar denitration process for Purex 1WW is provided. Experimental runs were made with a model annular circulator proposed for in-tank solidification of intermediate-level plant wastes to determine heat-transfer characteristics. Details of the engineering work on dehydration of fission product-loaded zeolites were documented. Equilibrium constants and free energies were determined for two exchange reactions on six exchangers. Zeolites with low silica-to-alumina ratios exhibited the highest strontium selectivity. Breakthrough curves for strontium on Linde 4A zeolite were predicted on the basis of plate theory and compared to experimentally determined curves. The calculated and experimental curves show close agreement. Work continued on defining flowsheet conditions for removal of cesium from Purex and Redox wastes. Experimental work is underway to evaluate electrodialysis as a processing technique for treatment of low- and intermediate- level wastes. Pilot plant solvent extraction studies were continued on the development of CSREX and D2EHPA processes for removal of long-lived heatgenerating fission products from Purex wastes. Pulse column design details are presented. (auth)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-18-004886
• OSTI ID: 4122528
• Report Number(s): HW-79140
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-64
• Country of Publication: United States
• Language: English

Related Subjects

WASTE DISPOSAL AND PROCESSING
ACIDITY
ADSORPTION
AMMONIA
CESIUM
CHEMICAL REACTIONS
CSREX PROCESS
DECOMPOSITION
DEHPA
DEHYDRATION
DENITRATION
DIAGRAMS
EFFICIENCY
EXTRACTION COLUMNS
HEAT TRANSFER
HEATING
IODINE
IODINE 131
ION EXCHANGE MATERIALS
LAYERS
NITRIC ACID
PHOSPHATES
PULSES
PUREX PROCESS
REDOX PROCESS
RUTHENIUM
SOLIDIFICATION
SOLVENT EXTRACTION
SPUTTERING
STRONTIUM
SUGARS
THERMODYNAMICS
TRACER TECHNIQUES
WASTE PROCESSING
WASTE SOLUTIONS
WATER
ZEOLITES