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On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators (open access)

On the Multiplication Constant of Homogeneous Mixtures of U with Various Moderators

The following represents a summary of calculations on the multiplication constant of homogeneous mixtures of uranium and different moderators. These calculations were made possible by Fermi's determination of the age of neutrons and by the extrapolation to higher scattering cross-sections of the resonance absorption of uranium as measured by C. Creutz. According to Fermi, the former quantity is 120 sq. cm. The latter is given in the two attached graphs. The first (Fig.1) of these goes as high as a scattering cross-section of 70 x 10-24 cm.2 per uranium atom, and its highest point is taken from a measurement of Cruetz's in which a mixture of U3O8 and graphite was used.
Date: May 16, 1943
Creator: Wigner, Eugene Paul, 1902-1995 & Stephenson, J.
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Errara for CC-918 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Errara for CC-918

Technical report listing the errata for pages 2, 4, 5, 6, 7, and 8 for report CC-918.
Date: October 16, 1943
Creator: Franck, J.
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Heavy Water, Report for the Month Ending May 1, 1944 (open access)

Metallurgical Laboratory, Chemical Research - Heavy Water, Report for the Month Ending May 1, 1944

Technical report with short reports on (1) Heavy water analysis and standardization, and Specific gravity of pure D2O; (2) Homogenous exponential experiment; (3) Recombination of pile gases; (4) Slurry pumping studies; and (5) Electron microscope laboratory.
Date: May 16, 1944
Creator: Hogness, T. R. (Thorfin Rusten), 1894-; Hiskey, C. F. & Eidinoff, Maxwell Leigh, 1915-
Object Type: Report
System: The UNT Digital Library
Preparation of U233 (open access)

Preparation of U233

Technical report. The object of the research is to determine the procedure and equipment for the preparation of U233 on a semi-works scale. The general proposed procedure is that thorium carbonate in aluminum cans will be irradiated with pile neutrons. The Pa233 resulting from neutron absorption the Th232 and the decay of Th233 will be extraction from 99% of the thorium and the natural U in thorium by MnO2 precipitations. The Pa233 will then be allowed to decay to U233 which in turn will be isolated from the remaining Th and partially decayed Pa233 by ether extraction.
Date: May 16, 1944
Creator: Apple, R. S.
Object Type: Report
System: The UNT Digital Library
Further End Cap Temperature Calculations (open access)

Further End Cap Temperature Calculations

Abstract. Recently (CP-1989) it has been shown that the neutron density, and thus the heat production, at the end of a slug with an A1 cap may be appreciably higher than that at the middle of the slag. A re-examination of earlier temperature calculations is made in light of this effect.
Date: August 16, 1944
Creator: Karush, William; Monk, A. T. & Wilkins, J. Ernest, Jr., 1923-2011
Object Type: Report
System: The UNT Digital Library
The Determination of T at the Dropping Mercury Electrode in Hex Plant Ammonia and Peroxide Decantrates (open access)

The Determination of T at the Dropping Mercury Electrode in Hex Plant Ammonia and Peroxide Decantrates

Inroduction: "A study of the literature, particularly the work done by R. Strubl, I.W. Kolthoff and S.B. Smith, indicated that a polargraphic method for the estimation of T could be devised which would not sacrifice reasonable accuracy for rapidity. Work was begun with the intention of developing such a method."
Date: January 16, 1945
Creator: Kwiatkowski, S.; Owens, J. & Casto, C. C.
Object Type: Report
System: The UNT Digital Library
Complexing Agents for the Solvent Extraction of Uranium from Thorium.  I. The Use of Thiocyanate in the Extraction of Uranium. II. The Use of Antipyrine in Solvent Extraction (open access)

Complexing Agents for the Solvent Extraction of Uranium from Thorium. I. The Use of Thiocyanate in the Extraction of Uranium. II. The Use of Antipyrine in Solvent Extraction

Abstract. In the first section of this technical report a new method of extracting uranium from thorium nitrate solution is discussed. This method consists of extracting an aqueous solution of thorium nitrate, nitric acid, sodium sulphate, and potassium thiocyanate with hexone. By this procedure, using an equal volume of hexone it is possible to extract 83 percent of the uranium while only 0.3 percent of the thorium is extracted. other experiments show that even greater separations are possible. In the second section of this report the use of antipyrine in solvent extraction procedures is discussed. Experiments are described in which 90 percent of the uranium is extracted while the thorium is extracted to the order of 3 to 5 percent.
Date: February 16, 1945
Creator: Reas, W. H.
Object Type: Report
System: The UNT Digital Library
A Rapid Method for Determination of Water in TO₃ (open access)

A Rapid Method for Determination of Water in TO₃

Summary: A set of conditions is described for a ten minute determination of water in TO₃ by ignition and absorption of the evolved water in magnesium perchlorate. Complete conversion to T₃O₃ is obtained under these conditions, so that total loss on ignition and total T (plus non-volatile impurity) content may also be obtained. It has been found unnecessary to employ Cu foil to prevent interference by nitrates, which may be present with a nitrate/water ratio as high as 5, and in an amount that does not exceed 100 mg.
Date: February 16, 1945
Creator: Barash, Bernard B.; Lee, Franklin B. & Curtiss, Edgar O.
Object Type: Report
System: The UNT Digital Library
The Laplacian for a Beryllium Metal Lattice of Volume Ratio 17.2 (open access)

The Laplacian for a Beryllium Metal Lattice of Volume Ratio 17.2

Abstract. the Laplacian of a beryllium metal lattice with 3.3 kg of uranium metal per cell and a volume ratio of 17.2 was measured in the removable region of the CP-2 machine. the sandwich effect with different moderators made interpretation of the observations very uncertain. The best result found was Be = 407 x 10(-6) cm(-2).
Date: January 16, 1946
Creator: Goldberger, Marvin L.; Wattenberg, Albert, 1917- & Zinn, Walter H. (Walter Henry), 1906-2000
Object Type: Report
System: The UNT Digital Library
Diameter Measurements of Slugs Before and After Prolonged Heat Treatment (open access)

Diameter Measurements of Slugs Before and After Prolonged Heat Treatment

Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."
Date: February 16, 1948
Creator: Bennett, Carl A. & Lane, J. J.
Object Type: Report
System: The UNT Digital Library
Summary of Surface Decontamination Experience at Oak Ridge National Laboratory: November 1943 Through July 1948 (open access)

Summary of Surface Decontamination Experience at Oak Ridge National Laboratory: November 1943 Through July 1948

"The experience at Oak Ridge National Laboratory in decontamination equipment and working areas from radioactivity has been summarized." The methods and reagents that were used for decontamination are discussed.
Date: September 16, 1948
Creator: Browder, F. N.
Object Type: Report
System: The UNT Digital Library
A Microdetermination of Uranium by Ferric Sulfate Titration (open access)

A Microdetermination of Uranium by Ferric Sulfate Titration

Abstract: "Following nitrate removal by means of a three-stage hydrochloric acid digestion, uranium was reduced with chromous sulfate reagent. In an inert atmosphere, the quadrivalent uranium was titrated at 80-95[degrees] with standard ferric sulfate solution. The end point was obtained with a potentiometric cell including a platinum in-titrant reference electrode and a platinum indicator electrode. Application was made to various low leverl uranium solutions. For samples containing 1 - 12 milligrams or uranium, less than one percent error may be expected. Iron and chromium do not interfere."
Date: February 16, 1949
Creator: Christopherson, E. W.
Object Type: Report
System: The UNT Digital Library
The Spectrochemical Analysis of Hafnium and Zirconium (open access)

The Spectrochemical Analysis of Hafnium and Zirconium

Abstract: "The analysis of hafnium and zirconium by the copper spark technique is presented for solutions of HCl, HF, and HClO4 acids. The special techniques of electrode protection and vacuum drying of perchloric acid samples are outlined. Also given are the working curves and deviations of both elements."
Date: March 16, 1949
Creator: Conway, John G. & Moore, Milton F.
Object Type: Report
System: The UNT Digital Library
The Coulometric Titration of 8-Hydroxyquinoline (open access)

The Coulometric Titration of 8-Hydroxyquinoline

Abstract: "A new method of determining 8-hydroxyquinoline by titration with electrolytucally-generated bromine has been developed. Results show good precision in the range 0.4 mg. to 1.6 mg. total 8-hydroxyquinoline, with 99% confidence limits of less than +/- 2%. An electronically-regulated constant current source, required by the method, is described. A new indicator system with high sensitivity to free bromine is discussed."
Date: June 16, 1949
Creator: Carson, W. N.
Object Type: Report
System: The UNT Digital Library
Power Recovery at Brookhaven ; Report No. 1 (open access)

Power Recovery at Brookhaven ; Report No. 1

From introduction: "This is the first report on the study made of the possible power recovery without excessive cost, from the operation of the Brookhaven reactor."
Date: June 16, 1949
Creator: Lucke, Charles Edward
Object Type: Report
System: The UNT Digital Library
The Coulometric Determination of Acetic Acid (open access)

The Coulometric Determination of Acetic Acid

Abstract: "Small amounts of acetic acid, equivalent to 400 ul. of 0.3 to 0.13 g/L. can be titrated coulonatrically in the presence of a 10 to 25-fold excess of HN03 in 70%, isopropanol. An accuracy of +/- 0.1% and a precision of +/- 8.5% (99% limite) are obtained.
Date: August 16, 1949
Creator: Carson, W. N. & Ko, Roy
Object Type: Report
System: The UNT Digital Library
Procedures in Magnetic Measurements at the University of California Radiation Laboratory, Berkeley:  Fields Which are Constant or Vary Slowly with Time (open access)

Procedures in Magnetic Measurements at the University of California Radiation Laboratory, Berkeley: Fields Which are Constant or Vary Slowly with Time

The flux standard is a device which will give a known flux-linkage change to be used as a calibration. At the Radiation Laboratory, two types of flux standards are used, a stationary type and a portable type.
Date: August 16, 1949
Creator: Richardson, Robert E.
Object Type: Report
System: The UNT Digital Library
Preparation of Ductile Zirconium: Summary of Thermodynamic Data (open access)

Preparation of Ductile Zirconium: Summary of Thermodynamic Data

Abstract: A summary of thermodynamic calculations for zirconium halides is given. Data indicates that the iodide is the most promising of the halides for arc dissociation and that good recoveries of zirconium should be obtainable provided dissociation is carried out at reduced pressure.
Date: September 16, 1949
Creator: Findlay, G. R.
Object Type: Report
System: The UNT Digital Library
Decontamination of Dissolver Vent Gases at Hanford (open access)

Decontamination of Dissolver Vent Gases at Hanford

The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.
Date: February 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
Object Type: Report
System: The UNT Digital Library
Laboratory Studies of the Pentaether Process for the Recovery and Decontamination of Uranium (open access)

Laboratory Studies of the Pentaether Process for the Recovery and Decontamination of Uranium

The following document reports the process of the recovery and decontamination of uranium using pentaether as the solvent extraction agent in a continuous flow system.
Date: February 16, 1951
Creator: Hicks, T. E.; Mayer, P. C. & Crandall, Howard William, 1921-1990
Object Type: Report
System: The UNT Digital Library
MTA Quarterly Progress Report:  September, October and November, 1951 (open access)

MTA Quarterly Progress Report: September, October and November, 1951

Quarterly report which includes brief summaries of research studies related to technology materials and accelerator testing
Date: February 16, 1951
Creator: Lawrence Radiation Laboratory
Object Type: Report
System: The UNT Digital Library
Some Physical and Chemical Properties of Curium (open access)

Some Physical and Chemical Properties of Curium

Report discussing improved methods of isolating and producing curium, as well as its density, the absorption spectrum of Cm⁺³, and the molar magnetic susceptibility of CmF₃.
Date: April 16, 1951
Creator: Crane, William Ward Turner
Object Type: Report
System: The UNT Digital Library
Process Engineering Report on Production of Thorium at Iowa State College (open access)

Process Engineering Report on Production of Thorium at Iowa State College

Technical report presenting the results of a study of the AEC thorium production facilities at Iowa State College, Ames, Iowa. Operating procedures, descriptions of equipment and a production cost analysis have been included in this study.
Date: January 16, 1952
Creator: Bulkowski, H. H.; Holby, G. V.; Pfeiffer, C.; Maerker, J. B. & Winn, F. W.
Object Type: Report
System: The UNT Digital Library
Bismuth Casting and Canning : (Information Report) (open access)

Bismuth Casting and Canning : (Information Report)

Introduction: The experimental work at Mound Laboratory on bismuth casting and the sealing of aluminum irradiation containers is an outgrowth of the bismuth recovery project. Since the recovered bismuth contains residual activity it is necessary that the bismuth be processed to the point that no contamination will result from shipment or any subsequent operations required to prepare the bismuth for irradiation. In order to satisfy these requirements the work here has consisted of investigating methods of preparing the bismuth slugs in the shapes required and of mechanically sealing the aluminum container.
Date: June 16, 1952
Creator: Engle, Paul
Object Type: Report
System: The UNT Digital Library