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Phase Transformations in Alumina. Technical Report, May to December 1961

Description: e transformation studies showed that synthetic aluminas produced in the laboratory were not transformed to alpha alumina at 400 to 700' deg n the presence of nitric acid and water vapor. Amorphous aluminn produced in the pilot plant was transformed to alpha alumina. This indicated that the amorphous alumina produced in the pilot plant is structurally predisposed to form alpha alumina. Most additives did not appear to have any special effects. Lithium formed zeta alumina, LiAl/sub 5/O/sub 8/. Ph… more
Date: December 1, 1961
Creator: Eding, H J; Huggins, M L & Brown, A G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests of a Vapor-Space Feed Nozzle for Calcining Aluminum Nitrate Solutions in a Fluidized Bed

Description: An investigation was conducted to determine the performance of a vapor- space feed nozzle which sprayed aluminum nitrate solution on the surface of a fluidized bed calciner. Results indicate that this type of feed system is satisfactory for calcining aqueous wastes from the processing of spent aluminum- type nuclear fueIs. Process and product control were achieved by adjusting the volumetric ratio of the air to the liquid fed to the nozzIe. The results obtained at various operating conditions a… more
Date: October 31, 1962
Creator: Lohse, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium from Slag and Crucible

Description: Slag and crucible can be dissolved satisfactorily by the Los Alamos method of total dissolution with nitric acid in the presence of aluminum nitrate. Extraction of 99% of the plutonium from total dissolution salted with aluminum nitrate was achieved by three successive contactings with 1/10 volumes of 30% TBp- AMSCO 125-90W. The TBPAMSCO phases contacted with leaching solutions salted with calcium nitrate must be scrubbed to remove calcium. Stripping with three 1/10 volumes of 0.1M hydroxylamin… more
Date: June 15, 1951
Creator: Groot, C.; Hopkins Jr., H. H. & Schulz, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of NP$sup 237$ by the Neptex Solvent-Extraction Process

Description: Flowsheets are presented for the solvent extraction recovery of uranium and Np/sup 237/ from special highly irradiated MTR fuel elements and from nonvolatile fluoride residues from the Oak Ridge Gaseous Diffusion Plant. In both cases the material containing the neptunium and uranium is dissolved and digested to inactivate emulsion-forming impurities, the neptunium and uranium are extracted with tributyl phosphate solvent, using aluminum nitrate as the primary salting agent, scrubbed free of fis… more
Date: April 1, 1957
Creator: Flanary, J. R.; Goode, J. H.; Mansfield, R. G. & Wischow, R. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technology of Non-Production Reactor Fuels Reprocessing Budget Activity 2790. Quarterly Report

Description: Sawing studies were made using a dry function blade for cutting Zircaloy taking. An off-gas filtration system including a rotoclone and a filter assembly was installed to permit studying of the particulate material generated during the friction cutting operations. Studies of mechanical techniques for safety processing the Na or NaK alloy reservoirs present in some non-production fuels have continued. Stainless steel-clad swaged U0/sub 2/ rods and stainless steel- clad U- 10 wt.% Mo alloy rods w… more
Date: July 1, 1959
Creator: Cooper, V. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phase Transformations in Calcination of Nitrates of Aluminum, Stainless Steel, and Nichrome

Description: Earlier studies showed that low concentrations of boric acid inhibit the formation of alpha alumina in the fluidized calcination of aluminum nitrate wastes. Studies designed to determine the optimum concentration of boric acid and the relative effectiveness of phosphoric acid were performed by heating synthetic mixtures at moderate pressure; results indicared that they were equally effective at the same molal concentration. Differential thermal analysis of mixtures showed that the boric acid re… more
Date: December 28, 1962
Creator: Eding, H J; Huggins, M L & Brown, A G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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KINETICS OF PARTICLE GROWTH IN A FLUIDIZED CALCINER

Description: Fluidized calcination involves the injection of an atomized feed solution containing dissolved solids into a bed of fluidized partioles at elevated temperatures suitable for drying and calcining. The study was conducted in a threeinch diameter fluidized column using aluminum oxide as bed material and aqueous aluminum nitrate solution as feed. Products were removed at regular intervals to maintain a constant bed weight. Particle growth was traced by adding radioactive aluminum oxide seeds of a g… more
Date: June 1, 1960
Creator: Lee, B. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MISCELLANEOUS EXPERIMENTS RELATING TO THE PROCESSING OF CETR FUEL BY SULFEX- THOREX AND DAREX-THOREX PROCESSES

Description: Experiments with unirradiated Consolidated Edison reactor ThO/sub 2/-- U0/sub 2/ fuel pellets indicated that uranium losses to Sulfex and Darex decladding solutions were proportional to the U0/sub 2/ content of the pellets. For example, after 7 hr, losses to boiling initial Darex solution (5 M HNO/sub 3/- -2 M HCl) were 0.45 and 0.65% from pellets containing 3 and 9% U0/sub 2/, respectively. The initial rate of dissolution of these pellets in 200% excess boiling 13 M HNO/sub 3/--0.04 M NaF-0.1 … more
Date: August 30, 1961
Creator: Ferris, L.M. & Kibbey, A.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Fluid-Bed Calculation of Radioactive Waste

Description: Liquid radioactive wastes are converted into solids, with volume reduction factors of 3 to 8, by flash drying on finely screened, porous, inert solid particles (e.g. alumina) in a fluidized bed at 320 to 550 deg C. The wastes may be either aluminum nitrate-containing wastes from the processing of MTR-type fuel elements, or Purex Process wastes. Ruthenium is found to be the only volatile fission product in this temperature range. Methods are described for its removal from the fluidizing gas. (T.… more
Date: May 1, 1961
Creator: Loeding, J. W.; Carls, E. L.; Anastasia, L. J. & Jonke, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Idaho Chemical Processing Plant Technical Progress Report for January- March 1960

Description: 9 > ? ( ing schedule included MTR, ETR, and other aluminum-type fuels that were processed through the TBP headend at 75 to 100% of flowsheet rates and through the Hexone second and third cycle extraction system at up to l5O% of flowsheet values, achieving an over-all recovery of 99.60%. In carrying out basic studies on aqueous zirconium processing, results obtained during the potentiometric titration of zirconium-fluoride-nitric acid solutions with sodium hydroxide were explained by a mechanism… more
Date: July 13, 1960
Creator: Slansky, C.M.; Warzel, F.M. & Bower, J.R. Jr. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION C, PROGRESS REPORT ON SEPARATIONS CHEMISTRY AND SEPARATIONS PROGRESS RESEARCH FOR JANUARY-JUNE 1963

Description: Cesium Recovery from Ores. Adaptation of the phenol extraction (Phenex) process to the recovery of cesium from ore leach liquors continued to show promise. In roast-leach tests, 98 to 99% of the cesium was dissolved from pollucite ore by roasting the ore at 800 deg C with 1.8 parts of Na/sub 2/CO/sub 3/ plus 1.2 parts of NaCl and leaching with water. More than 99% of the cesium was recovered from the leach liquor and separated from other alkali metals by extracting with 4-sec-butyl-2-( alpha -m… more
Date: October 25, 1963
Creator: Brown, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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