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

Abstract

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 experimentalmore » 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)« less

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

Citation Formats

Irish, E.R. ed. RESEARCH AND DEVELOPMENT ACTIVITIES FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, July-September 1963. United States: N. p., 1963. Web. doi:10.2172/4122528.
Irish, E.R. ed. RESEARCH AND DEVELOPMENT ACTIVITIES FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, July-September 1963. United States. https://doi.org/10.2172/4122528
Irish, E.R. ed. Tue . "RESEARCH AND DEVELOPMENT ACTIVITIES FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, July-September 1963". United States. https://doi.org/10.2172/4122528. https://www.osti.gov/servlets/purl/4122528.
@article{osti_4122528,
title = {RESEARCH AND DEVELOPMENT ACTIVITIES FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, July-September 1963},
author = {Irish, E.R. ed.},
abstractNote = {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)},
doi = {10.2172/4122528},
url = {https://www.osti.gov/biblio/4122528}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {10}
}