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Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Description: Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as ninety percent hafnium, can be made available with little additional cost.
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Partner: UNT Libraries Government Documents Department

Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Description: Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Partner: UNT Libraries Government Documents Department

Development and Properties of Uranium Monocarbide Cermets : Final Report

Description: Abstract: "Uranium monocarbide-Zircaloy II alloy cermets were developed and tested for chemical and physical properties. It was determined that pure uranium monocarbide can be prepared by vacuum are melting techniques. Following melting, the combination, hot pressing, and corrosion behavior of dense monocarbide has been studied. The preparation of uranium monocarbide-Zircaloy II cermet bodies was investigated by means of hot pressing, cold pressing and sintering, warm pressing, extrusion, and hot rolling. The corrosion resistance of the cermets was related to such variables as composition, preparation technique, and powder size. 01 per cent uranium monocarbide, 70 per cent zircaloy II cermets withstood corrosion tests in 680 F water. Cermets having above 30 weight per cent uranium monocarbide were not corrosion resistant."
Date: September 17, 1956
Creator: McGee, S. W. & Sump, C. H.
Partner: UNT Libraries Government Documents Department

Hydrogen Peroxide Analysis and Decomposition in Chromate Solutions

Description: Abstract: "A novel procedure employing ion exchange resins was developed to separate chromate ions from hydrogen peroxide, permitting, permitting the subsequent analysis of peroxide to determine its decomposition in sodium chromate solutions. At high pH's, peroxide was absorbed anionically on the ion exchange resins along with chromate. By selecting a resin which would be effective at nearly neutral conditions, chromate was satisfactorily separated from peroxide. It was found that the rate of peroxide decomposition in slightly alkaline sodium chromate solutions was dependent on temperature, pH, aeration, and chromate concentration. No significant effect on decomposition was caused by visible light."
Date: March 17, 1952
Creator: Rynasiewicz, Joseph & Ryan, J. W.
Partner: UNT Libraries Government Documents Department

Loop-Type Liquid-Gas Separator

Description: The following report is a study of the separating qualities of a loop-type separator that can obtain separation with a smaller pressure drop.
Date: November 17, 1951
Creator: Barlow, J. W.; Jones, F. H. & Reuther, R. H.
Partner: UNT Libraries Government Documents Department

Further Critical Experiments on a Small Reactor of Enriched U-235 with Al-H₂O Moderator and Beryllium Reflector

Description: From introduction: "The purpose of the present report is to describe briefly certain improvements that have been made in the experimental facilities and to present the results of further measurements on critical masses and spatial neutron flax distributions in Be reflected reactors having square and thin slab geometries."
Date: August 17, 1948
Creator: Martin, A. B. & Mann, M. M.
Partner: UNT Libraries Government Documents Department

Analytical studies of the estimation of beryllium oxide in beryllium metal

Description: From abstract: The estimation of beryllium oxide in beryllium metal depending on the differential solubilities of the two material in dilute hydrochloric acid is presented. The results compare favorably with the present beryllium chloride volatilization procedure. Alternate methods are described, and the limitations and possible errors are discussed.
Date: April 17, 1951
Creator: Rynasiewicz, Joseph
Partner: UNT Libraries Government Documents Department

Some Effects of Irradiation on Metals

Description: Report discussing several experiments investigating the effect of radiation on metals, specifically on intermetallic diffusion, mechanical properties of 347 stainless steel and electric resistance of 347 stainless steel.
Date: 1952-03-17?
Creator: Parkins, W. E.
Partner: UNT Libraries Government Documents Department

Safety Analysis of the Storage and Handling of the SRE Fuel

Description: "The most hasardous conditions relating to the storage and handling of the SRE fuel are those in which water and fuel form a possible critical assembly. Therefore, this memorandum is primarily devoted to an analysis of the conditions necessary for a critical mixture of water and SRE fuel. Certain special geometries are then analyzed for their safeness."
Date: November 17, 1954
Creator: Williams, R. O.
Partner: UNT Libraries Government Documents Department

Materials Testing Reactor Project : Addendum to Reactor Building Report, Design Report No. 26A

Description: "Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, ANL and ORNL. The changes are listed in accordance with the main headings, pages and paragraphs to which they apply."
Date: November 17, 1949
Creator: Link, L. E. & Guzik, R. F.
Partner: UNT Libraries Government Documents Department

Recovery of Uranium From Contaminated Precipitron Oil

Description: Abstract: The distillation and residue extraction recovery procedures developed for the recovery of uranium from Kinney and diffusion pump oil, were applied to contaminated precipitron oil. The effectiveness and advisability of using the method, in whole or in part, is discussed, and various recommendations for processing this particular type of oil are presented. Additional contaminating substances present in this type of oil added to the complexity of the problem but a satisfactory recovery procedure was, nevertheless, successfully developed.
Date: April 17, 1947
Creator: Lee, J. E.; Aikin, L. M. & Susano, C. D.
Partner: UNT Libraries Government Documents Department

Coulometric Titration Plutonium

Description: Abstract:"A method is described for the electroreduction of plutonium to the +3 valence state in a nitric acid-sulfamic acid solution. Exploratory experiments in the search for a coulometric titration of Pu(III) using electrolytically generated ceric ion are also described. The results strongly indicate that a convenient procedure can be devised. Suggestions for future work are presented."
Date: February 17, 1953
Creator: Dreeben, A. B.
Partner: UNT Libraries Government Documents Department

The Effect of Temperature on the Distribution of Nitric Acid Between Dibutyl Carbitol and Aqueous Solutions of Copper Nitrate

Description: This report follows a test made to determine the effect of temperature on the distribution of nitric acid between "carbitol" and gunk, extracting a number of samples of aqueous copper nitrate with samples of "carbitol" of various acidities. The data obtained is covered in Table 1.
Date: January 17, 1946
Creator: Shacklett, C. D. & Wilcox, W. J., Jr.
Partner: UNT Libraries Government Documents Department