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Title: CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1959

Abstract

4 -Metallurgical Processing. A direct-cycle fuel reprocessing plant is being designed for pyrometaliurgical processing of discharged power reactor fuel elements. Irradiation tests on cerium-bearing glass samples for shielding windows revealed that the optimum cerium content is less than the nominal amount originally specified. The light output of gammairadiated mercury vapor lamps was determined to be about 55% of original after an exposure of 1.1 x 10/sup 9/ rads. Analyses of the composition of 30 ten-kilogram ingots of natural U-5% fissium alloy prepared in the melt-refining furnace indicate that not all of the added Zr and Mo went into solution. Irradiation tests have shown that natural rubber formulated with an antioxidant (Antiox 4010) is satisfactory for cable insulation at radiation levels to 2 x 10/sup 8/ rads. Four 2-kilogram scale runs were made to study the meltrefining characteristics of high Pu (20%) -- U --flssium alloys. A further investigation was made of the possible Zr contamination of molten U and its Ce alloy resulting from prolonged holding at 1400 deg C in stabilized ZrO/sub 2/ crucibles. Experiments at 1700 deg C showed considerable evolution of CO as a result of reaction of ZrO/sub 2/ with graphite. Reduction of oxide coatings onmore » U fuel pins by Mg in Zn solution continues to be promising. Studies were continued on the processing of melt-refining residues. Engineering techniques are being developed and evaluated for the various liquid metal procesaes under consideration. Further evidence of attack of Ta by Zn at 800 deg C is reported. In 100hour tests at 550 deg C, Cd containing up to l0 n did not corrode mild steel. The solubilitiea of La, Pd, Zr, and Mo in liquid Cd were measured. The Pd and Zr solubilities were also examined for U-saturated Cd solutions. The solubility of U in Cd-Zn, Cd-bg. Cd-Mg, and Zn-Mg alloys was investigated. The coefficient for the coprecipitation of Pu with U from Cd solutions is 0.67. The preparation of a high-purity sample of each of two forms of molybdenum sulfide was completed. Fuel Cycle Applications of Volatility and Fluidization Techniques. In connection with the reprocessing of reactor fuels by combined fluidizationvolatility processes, the fluorination rates of UF/sub 4/ by mixtures of fluorine and helium were investigated. Additional studies were made of the effect of ADF process variables on the recovery of U from U-Zr and Zircaloy-2 fuel alloys. Batch fluid-bed fluorinations of fluid-bed dried material were made in the 2 1/2-inch diameter unit at 500 deg C. Dvelopment work continued on a high-temperature fused-salt process for the recovery of enriched U from Zr matrix fuel alloys. The exchange of Zr between irradiated Zr dissolved in Bi and molten fused fluoride salt, as well as the extent of the extraction of Zr and Hb by the fused salt, is demonstrated. Additional data are reported from the operation of the fluid-bed waste calciner, used to convert liquid wastes to granular solids. Feasibility studies have started on the direct continuous conversion of UFB to UO/sub 2/ by reaction with steam and hydrogen in a l 1/2- inch diameter fluidized bed. The planned series of experiments on the mixing of solids in straight- and tapered-wall fluid-bed columns using a radioactive tracer technique was completed. Reactor Safety. In the studies of the rate of propagation of burning along U foils, a large number of surface contaminants have been shown to have no effect or to slow the burning process in air. The experimental program to determine rates of reaction of molten reactor fuel and cladding metals with water is continuing. Reactor Chemistry. Studies on the decontamination of boiling water reactors« less

Publication Date:
Research Org.:
Argonne National Lab., Lemont, Ill.
OSTI Identifier:
4228893
Report Number(s):
ANL-5996
NSA Number:
NSA-13-016869
DOE Contract Number:  
W-31-109-ENG-38
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; BISMUTH; CADMIUM; CADMIUM ALLOYS; CARBON MONOXIDE; CERIUM; CHEMICAL REACTIONS; COMBUSTION; CONTAMINATION; CORROSION; DECONTAMINATION; ELECTRIC CONDUCTIVITY; ENRICHMENT; FLUIDIZATION; FLUORIDES; FLUORINATION; FLUORINE; FUEL ELEMENTS; FUELS; FURNACES; FUSED SALTS; GAMMA RADIATION; GLASS; GRAPHITE; HELIUM; HIGH TEMPERATURE; HYDROGEN; IMPURITIES; IRRADIATION; LANTHANUM; LIQUIDS; MAGNESIUM; MAGNESIUM ALLOYS; MATRICES; MELTING; MERCURY; MERCURY ALLOYS; METALLURGY; MOLYBDENUM; MOLYBDENUM SULFIDES; NIOBIUM; OXIDATION; OXIDES; PALLADIUM; PLUTONIUM; POWER PLANTS; PRECIPITATION; PRODUCTION; QUANTITY RATIO; RADIATION DOSES; RADIOACTIVITY; REACTORS; RECOV

Citation Formats

. CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1959. United States: N. p., 1959. Web. doi:10.2172/4228893.
. CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1959. United States. https://doi.org/10.2172/4228893
. Mon . "CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1959". United States. https://doi.org/10.2172/4228893. https://www.osti.gov/servlets/purl/4228893.
@article{osti_4228893,
title = {CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR JANUARY, FEBRUARY, MARCH 1959},
author = {},
abstractNote = {4 -Metallurgical Processing. A direct-cycle fuel reprocessing plant is being designed for pyrometaliurgical processing of discharged power reactor fuel elements. Irradiation tests on cerium-bearing glass samples for shielding windows revealed that the optimum cerium content is less than the nominal amount originally specified. The light output of gammairadiated mercury vapor lamps was determined to be about 55% of original after an exposure of 1.1 x 10/sup 9/ rads. Analyses of the composition of 30 ten-kilogram ingots of natural U-5% fissium alloy prepared in the melt-refining furnace indicate that not all of the added Zr and Mo went into solution. Irradiation tests have shown that natural rubber formulated with an antioxidant (Antiox 4010) is satisfactory for cable insulation at radiation levels to 2 x 10/sup 8/ rads. Four 2-kilogram scale runs were made to study the meltrefining characteristics of high Pu (20%) -- U --flssium alloys. A further investigation was made of the possible Zr contamination of molten U and its Ce alloy resulting from prolonged holding at 1400 deg C in stabilized ZrO/sub 2/ crucibles. Experiments at 1700 deg C showed considerable evolution of CO as a result of reaction of ZrO/sub 2/ with graphite. Reduction of oxide coatings on U fuel pins by Mg in Zn solution continues to be promising. Studies were continued on the processing of melt-refining residues. Engineering techniques are being developed and evaluated for the various liquid metal procesaes under consideration. Further evidence of attack of Ta by Zn at 800 deg C is reported. In 100hour tests at 550 deg C, Cd containing up to l0 n did not corrode mild steel. The solubilitiea of La, Pd, Zr, and Mo in liquid Cd were measured. The Pd and Zr solubilities were also examined for U-saturated Cd solutions. The solubility of U in Cd-Zn, Cd-bg. Cd-Mg, and Zn-Mg alloys was investigated. The coefficient for the coprecipitation of Pu with U from Cd solutions is 0.67. The preparation of a high-purity sample of each of two forms of molybdenum sulfide was completed. Fuel Cycle Applications of Volatility and Fluidization Techniques. In connection with the reprocessing of reactor fuels by combined fluidizationvolatility processes, the fluorination rates of UF/sub 4/ by mixtures of fluorine and helium were investigated. Additional studies were made of the effect of ADF process variables on the recovery of U from U-Zr and Zircaloy-2 fuel alloys. Batch fluid-bed fluorinations of fluid-bed dried material were made in the 2 1/2-inch diameter unit at 500 deg C. Dvelopment work continued on a high-temperature fused-salt process for the recovery of enriched U from Zr matrix fuel alloys. The exchange of Zr between irradiated Zr dissolved in Bi and molten fused fluoride salt, as well as the extent of the extraction of Zr and Hb by the fused salt, is demonstrated. Additional data are reported from the operation of the fluid-bed waste calciner, used to convert liquid wastes to granular solids. Feasibility studies have started on the direct continuous conversion of UFB to UO/sub 2/ by reaction with steam and hydrogen in a l 1/2- inch diameter fluidized bed. The planned series of experiments on the mixing of solids in straight- and tapered-wall fluid-bed columns using a radioactive tracer technique was completed. Reactor Safety. In the studies of the rate of propagation of burning along U foils, a large number of surface contaminants have been shown to have no effect or to slow the burning process in air. The experimental program to determine rates of reaction of molten reactor fuel and cladding metals with water is continuing. Reactor Chemistry. Studies on the decontamination of boiling water reactors},
doi = {10.2172/4228893},
url = {https://www.osti.gov/biblio/4228893}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {6}
}