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Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945

Technical report with short reports covering (1) Effect of radiation on water and aqueous systems; (2) Effect of neutrons on graphite; (3) Effect of radiation on solid compounds; and (4) Scattering, stopping-power, ion-pair production, etc.
Date: February 1, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
Object Type: Report
System: The UNT Digital Library
A Method of Recovering Thorium from Slag Materials (open access)

A Method of Recovering Thorium from Slag Materials

Abstract. a method of recovering thorium from slag from the bomb process of producing thorium has been developed. HCl and NaOH are the only chemicals required in quantity. Materials required for a representative slag are given.
Date: March 23, 1945
Creator: Johnson, Oliver & Fisher, R. W.
Object Type: Report
System: The UNT Digital Library
Chemical Research -- Extraction and Properties of U233; Report for the Period Ending December 15, 1944 (open access)

Chemical Research -- Extraction and Properties of U233; Report for the Period Ending December 15, 1944

Technical report containing short articles on (1) Determination of physical constants for U233; (2) Determination of decay chain of U233; (3) Extraction of U233; (4) Extracting solvents for uranium; (5) Factors affecting the extraction uranium and thorium by organic solvents, especially ether; and (6) Analysis of ore samples for protoactinium.
Date: February 24, 1945
Creator: Seaborg, Glenn T. (Glenn Theodore), 1912-1999; Manning, F. M. & Katzin, L. I.
Object Type: Report
System: The UNT Digital Library
Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2] (open access)

Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]

Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium metal upon treatment with various acids and upon fusion withKHSO4 is described. three satisfactory procedures are given for dissolving the metal with sulfuric acid, phosphoric acid, and by a potassium hydrogen sulfate fusion. The laboratory was presented with the problem of analyzing for a large number of elements in O2 metal. the results of a systematic study of methods for effecting solution of the metal are offered here since they may be of some interest and use to other laboratories. The four methods which effected complete solution of the metal are (1) Sulfuric acid method; (2) Fusion method; (3) Phosphoric acid method; and (4) Nitric acid-hydrofluoric acid method.
Date: January 1, 1945
Creator: Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
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
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending March 15, 1945 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending March 15, 1945

Technical report with short reports on (1) Effect of radiation on water and aqueous systems; (2) Gas evolution from uranyl solutions; (3) Effect of radiation on solid compounds; (4) Instruments; and (5) Scattering.
Date: March 15, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
Object Type: Report
System: The UNT Digital Library
Analysis of Iron in Thorium, Beryllium, and Cerium (open access)

Analysis of Iron in Thorium, Beryllium, and Cerium

Introduction. the colorimetric determination of iron based on the formation of the colored ferrous-1,10-phenanthroline complex has been used successfully by a number of investigators. In this technical report, its adaptation to the routine determination of iron in cerium, thorium, and beryllium metals and their compounds is described.
Date: September 10, 1945
Creator: Ericson, R. P & Fornefeld, E. J.
Object Type: Report
System: The UNT Digital Library
The Spectrographic Analysis of Beryllium and its Compounds (open access)

The Spectrographic Analysis of Beryllium and its Compounds

Abstract. Spectrographic procedures for determining small amounts of the common contaminants in beryllium and its compounds are described. Suggestions relative to the preparation of synthetic standards are also given.
Date: June 22, 1945
Creator: Smith, A. Lee (Albert Lee), 1924-
Object Type: Report
System: The UNT Digital Library
Extraction of Uranyl Nitrate and Thorium Nitrate by Organic Solvents (open access)

Extraction of Uranyl Nitrate and Thorium Nitrate by Organic Solvents

Abstract. The separation of uranyl nitrate from aqueous solutions of 0.635 M thorium nitrate, 3 M nitric acid and 3 M calcium nitrate by extraction with organic solvents has been investigated. Solvents which gave good separations were 2-tthyl hexyl acetate, ethyl benzoate, n-butyl either and beta-beta- dichloroethyl ether. In general, higher esters, ethers and alcohols are better for separating uranium from thorium that the lower homologues. Several solvents were tested at lower nitric acid concentrations. Dibutyl cellosolve gave a very good separation when the solution was 0.1 M nitric acid. Of the solvent mixtures studied that of equal parts of n-butyl ether and dibutyl cellosolve gave a good separation.
Date: November 5, 1945
Creator: Johnson, O. & Newton, A. S.
Object Type: Report
System: The UNT Digital Library
Precipitation of Thorium Oxalate from Nitric Acid Solutions (open access)

Precipitation of Thorium Oxalate from Nitric Acid Solutions

Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended two per cent mineral acid, it would be advantageous to be able to quantitatively remove the thorium without otherwise altering the solutions. This was especially of interest in solutions containing bismuth, since it was hoped that some amounts of thorium could be precipitated in nitric acid solutions containing large quantities of bismuth. In removing the bismuth, first by a bismuth oxychloride precipitation, thee is every opportunity for carrying of the thorium.
Date: October 5, 1945
Creator: Ayers, A. S.
Object Type: Report
System: The UNT Digital Library
The Extraction of Uranium into Hexone as Uranyl Thiocyanate from Thorium Nitrate Solutions (open access)

The Extraction of Uranium into Hexone as Uranyl Thiocyanate from Thorium Nitrate Solutions

Technical report with six sections describing the process: (1) The reaction of HN)3 with HSCN; (2) The distribution of nitric acid between hexone and water; (3) The distribution of HSCN between hexone and water; (4) The solubility of thorium sulfate in various extraction solutions; (5) The distribution of protoactinium and fission elements between hexone and aqueous thiocyanate solutions; and (6) Separation of uranium from thorium by extraction into hexone as UO2(SCH)a.
Date: May 18, 1945
Creator: Reas, William H.
Object Type: Report
System: The UNT Digital Library
Sweeping of Fission Gases from Solutions of U and Plutonium (open access)

Sweeping of Fission Gases from Solutions of U and Plutonium

Technical report describing two experiments performed to compare the amounts of fission gases swept out of UNH solution with those amounts swept out of PU solution under idential condiditons. The charge wire technique was used. The essential date and the results are given in tables in the report.
Date: September 4, 1945
Creator: Adams, R. M. & Finkelstein, H.
Object Type: Report
System: The UNT Digital Library
The Rapid Determination of Nitric Acid and Thorium in Thorium Nitrate Solutions (open access)

The Rapid Determination of Nitric Acid and Thorium in Thorium Nitrate Solutions

Abstract. The physico-chemical methods of determining nitric acid and thorium nitrate in solutions containing these two materials were investigated. Conductimetric titration with sodium hydroxide can be used to determine nitric acid accurately. the titration of thorium nitrate requires a separate standardization of the base however, since a basic salt is precipitated rather the normal hydroxide. The titration of thorium is reproductible however, so and empirical standardization can be used. The measurement of the specific gravity and refractivity of the solutions provides a method of determining the concentrations in terms of these two variable. Equations for the concentrations in terms of specific gravity and refractively are given, both in pure solutions and in those saturated with methyl isobutyl ketone.
Date: November 27, 1945
Creator: Newton, A. S.; Powell, J. (James), 1932- & Figard, P
Object Type: Report
System: The UNT Digital Library
Recovery of D2O and UO2F2 by Distillation (open access)

Recovery of D2O and UO2F2 by Distillation

Technical report describing the purification and separation by distillation of UO2F2 from D2O. In the experiment which is discussed 2,129.6 lbs of UO2F2 were dissolved in 6,605 lbs of D2O. The average isotopic purity of the D2O decreased during the distillation from 99.77% to 99.73%. The dissolved impurities were less than those present originally in the heavy water.
Date: October 10, 1945
Creator: Fischer, R. & Wattenberg, Albert, 1917-
Object Type: Report
System: The UNT Digital Library
A Study of Thorium Peroxide Sulfate (open access)

A Study of Thorium Peroxide Sulfate

Abstract. Thorium peroxide was precipitated from thorium nitrate solutions containing varying amounts of sulfate ion and of hydrogen ion. The washed solids were analyzed both wet and dry. Analyses were made for thorium, peroxide oxygen, sulfate, nitrate, and water contents. X-ray powder photographs of the dried samples by W.H. Zachariasen showed the presence of only two phases. When precipitated from high sulfuric acid, the solid phase was isomorphous with Th(OO)SO4.3H20. More weakly acid solutions whose sulfate content was varied over wide limits [SO4--/Th(IV) (in solution before precipitation) = 0.005 to 67.0] yielded a solid, isomorphous with thorium peroxide nitrate and containing 3.0 to 3.8 peroxide oxygen atoms for each thorium atom. The sulfate content of this latter phase varied continuously between the limits SO4--/Th(IV) = 0.34 to 0.01 with nitrate ion present when the sulfate content was very low. This continuous variation in composition is in agreement with the previously proposed structure of this phase.
Date: October 1, 1945
Creator: Hamaker, John W.
Object Type: Report
System: The UNT Digital Library
The Production of Ceramic Ware by Slip-Casting (open access)

The Production of Ceramic Ware by Slip-Casting

This report discusses the production of ceramic ware through the process of slip-casting. The report separately describes the processes of creating zirconia ware, beryllia ware, alundum ware, thoria ware, and specially shaped ceramic ware.
Date: October 20, 1945
Creator: Calderwood, Wayne
Object Type: Report
System: The UNT Digital Library
Note: Positive Ion Gun for the Notre Dame Van de Graaff-Herb Generator (open access)

Note: Positive Ion Gun for the Notre Dame Van de Graaff-Herb Generator

"This report is based on work done at the University of Notre Dame under the auspice of the Manhattan District under contract No. W-7405-Eng-49." This report discusses the operation and purpose of the positive ion gun for the Notre Dame's Van de Graaf-herb generator
Date: 1945
Creator: Wiedenbeck, M. L.
Object Type: Report
System: The UNT Digital Library
Studies of Porphyrin Metabolism, 3. The Relation of Erythropoiesis to the Excretion of Coproporphyrin by Dogs and Rabbits, and to the Concentration of Coproporphyrin and Protoporphyrin in Rabbit Erythrocytes (open access)

Studies of Porphyrin Metabolism, 3. The Relation of Erythropoiesis to the Excretion of Coproporphyrin by Dogs and Rabbits, and to the Concentration of Coproporphyrin and Protoporphyrin in Rabbit Erythrocytes

Report discussing studies regarding porphyrin excretion and hemoglobin metabolism in animals with phenylhydrazine anemia, and studies regarding the coproporphyrin and protoporphyrin in the red blood cells of rabbits.
Date: November 25, 1945
Creator: Schwartz, Samuel; Glickman, Marcia; Hunter, Rosie & Wallace, Jean
Object Type: Report
System: The UNT Digital Library
Interval Between Pulses of Counter or Scaler (open access)

Interval Between Pulses of Counter or Scaler

This paper is based off of an operation of a recording tape scaler, which records pulses from a counter or scaler upon a tape as a function of time. With the recording tape scaler, the interval between pulses of counter or scaler is measured in this report.
Date: 1945
Creator: Coveyou, R. R.
Object Type: Report
System: The UNT Digital Library
Testing of Counter-Scaler Units for Statistics (open access)

Testing of Counter-Scaler Units for Statistics

Report discussing the results of an investigation of a test for statistical consistency of counter-scaler units.
Date: January 1, 1945
Creator: Coveyou, R. R.
Object Type: Report
System: The UNT Digital Library
The Solubility of Uranyl Oxalate and the Existence of Undissociated Uranyl Oxalate in Solution (open access)

The Solubility of Uranyl Oxalate and the Existence of Undissociated Uranyl Oxalate in Solution

Abstract: "The solubility of the solid, UO2C2O4 x rH2O, was measured at various acid and uranyl nitrate concentrations. The results of the measurements prove the existence of the uranyl oxalate complex - UO2C2O4, in solutions containing excess UO2^2."
Date: September 8, 1945
Creator: Pimentel, George C. & Stevenson, F. R.
Object Type: Report
System: The UNT Digital Library

Pulse Unit Model 1

Technical drawing of pulse circuits for use in nuclear reactors.
Date: 1945
Creator: Titterton, E. W.
Object Type: Technical Drawing
System: The UNT Digital Library

Video Amplifier & Scope

Technical drawing of video amplifiers for nuclear reactors.
Date: 1945
Creator: Titterton, E. W.
Object Type: Technical Drawing
System: The UNT Digital Library

Battery Operated Field Pulser

Technical drawing of pulse generators for use in nuclear reactors.
Date: 1945
Creator: Titterton, E. W.
Object Type: Technical Drawing
System: The UNT Digital Library