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

Abstract

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 notmore » 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)« less

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

Citation Formats

Irish, E.R. ed. RESEARCH AND DEVELOPMENT ACTIVITIES ON FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, April-June 1963. United States: N. p., 1963. Web.
Irish, E.R. ed. RESEARCH AND DEVELOPMENT ACTIVITIES ON FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, April-June 1963. United States.
Irish, E.R. ed. Mon . "RESEARCH AND DEVELOPMENT ACTIVITIES ON FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, April-June 1963". United States.
@article{osti_4634965,
title = {RESEARCH AND DEVELOPMENT ACTIVITIES ON FIXATION OF RADIOACTIVE RESIDUES. Quarterly Progress Report, April-June 1963},
author = {Irish, E.R. ed.},
abstractNote = {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)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {7}
}

Technical Report:
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