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The Determination of Fluoride in Plutonium Metal by Thorium Titration (open access)

The Determination of Fluoride in Plutonium Metal by Thorium Titration

Abstract: "A titrimetric method for the determination of fluoride in plutonium is reported. Prior to a steam distillation of the fluoride, the bulk of the plutonium is separated by precipitation of the sulfate. The fluoride in the distillate is titrated at a pH of 3.2 with 0.001 M thorium nitrate, using chrome azurol-S indicator. Applied to samples containing 1 to 15 parts per million fluoride, the recovery is 87% and the precision on the 95% confidence level is +/- 0.65 ppm."
Date: May 4, 1954
Creator: Ferguson, W. S. & Newell, D. M.
Object Type: Report
System: The UNT Digital Library
A Study of the Radiation Burst in the Hanford Homogeneous Reactor (open access)

A Study of the Radiation Burst in the Hanford Homogeneous Reactor

Report discussing the details of a radiation burst in a spherical reactor using plutonium nitrate fuel that occurred on November 16, 1951 at Hanford Works.
Date: May 2, 1952
Creator: Leonard, B. R., Jr.
Object Type: Report
System: The UNT Digital Library
Current Beryllium Literature : A Selected Bibliography, August 1959 - December 1969 (open access)

Current Beryllium Literature : A Selected Bibliography, August 1959 - December 1969

"This bibliography lists selected books, articles, and unclassified reports which have appeared in the following abstracts and indexes between August 1959 and December 1960."
Date: May 1, 1961
Creator: Lane, Zanier D.
Object Type: Report
System: The UNT Digital Library
Toy Top Plasma Injector (open access)

Toy Top Plasma Injector

Introduction: "It is the purpose of this note to describe the construction and operation of the plasma injectors used in the magnetic high compression experiments in progress at the Lawrence Radiation Laboratory at Livermore. As the investigations of these injections is still in progress, remarks concerning their operation or the characteristics of the injected plasma are of a tentative nature."
Date: May 28, 1959
Creator: Coensgen, F. H.; Cummins, W. & Sherman, A.
Object Type: Report
System: The UNT Digital Library
Radiation Effects, Quarterly Progress Report, October-December 1953 (open access)

Radiation Effects, Quarterly Progress Report, October-December 1953

None
Date: May 15, 1954
Creator: Faris, F. E.
Object Type: Report
System: The UNT Digital Library
Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954 (open access)

Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

"A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distributed source of thermal neutrons upon slowing down in the lattice."
Date: May 15, 1954
Creator: Laubenstein, R. A.
Object Type: Report
System: The UNT Digital Library
Radiation Effects, Quarterly Progress Report, January-March 1954 (open access)

Radiation Effects, Quarterly Progress Report, January-March 1954

None
Date: May 24, 1954
Creator: Faris, F. E.
Object Type: Report
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943

Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.
Date: May 15, 1943
Creator: Franck, J.
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
Mass Spectrometric Evidence for the Pyridoxal-Leucine Reaction Mechanism (open access)

Mass Spectrometric Evidence for the Pyridoxal-Leucine Reaction Mechanism

From Abstract : "The mass spectrum of leucine-dn, prepared by the reaction of pyridoxal with excess leucine in D2O medium, has been established using the crucible source techniques. ... The reaction can be used for the selective α, β-deuteration of amino acids other than leucine.
Date: May 3, 1963
Creator: Junk, G. A. & Svec, H. J.
Object Type: Report
System: The UNT Digital Library
Reinvestigation of the CC Stretching and CH3 Rocking Assignments In Isopropyl and tert-Butyl Halides (open access)

Reinvestigation of the CC Stretching and CH3 Rocking Assignments In Isopropyl and tert-Butyl Halides

From report: "In a series of paper (1-3) Sheppard has analyzed the vibrational spectra of simple alkyl halides. During the course of an investigation of the spectra of similar alkyl thiocyanates certain anomalies appeared in the assignments of the CC stretching and methyl rocking vibrations in isopropyl and tert.-butyl halides."
Date: May 3, 1963
Creator: Hirschmann, R. P. & Kniseley, R. N.
Object Type: Report
System: The UNT Digital Library
Braze Alloys v.s. Atmospheres : Final Report Project 1325 (open access)

Braze Alloys v.s. Atmospheres : Final Report Project 1325

Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer
Date: May 21, 1959
Creator: Rogers, S. L.
Object Type: Report
System: The UNT Digital Library
Weldability of Hayes Alloy #25 (open access)

Weldability of Hayes Alloy #25

Technical report describing the process to determine the fusion welding characteristics of Haynes Alloy #25 as applied to TLJ-100530, Corrosion Loops. Hayes Stellite Alloy #25 is a cobalt-base alloy for corrosion resistant high temperature applications. This material, when welded by the inert gas shielded tungsten arc method, produces sound ductile joints. Material thicknesses greater than 12 gauge require standard joint preparations, a V joint being preferred up to 1/4 inch and a U joint for greater thicknesses. Welding heat should be kept to a minimum followed by fast cooling. The molten metal is very fluid and may present difficulties when position welding.
Date: May 19, 1959
Creator: Rogers, S. L.
Object Type: Report
System: The UNT Digital Library
The Effect of Fast Fission on k (open access)

The Effect of Fast Fission on k

The importance of fast neutron fission (i.e., fission caused by neutrons before being slowed down) was recognized by Szilard, and calculations similar to the present one have already been carried out by him, Feld, Ashkin, Wheeler, Wigner and others. The purpose of the present paper is to give a general formula for the contribution of fast fission to the multiplication constant, which will include all the cases already considered and will be applicable to more complicated geometries than those considered by the previous writers.
Date: May 4, 1943
Creator: Castle, H.; Ibser, H.; Sacher, G. & Weinberg, Alvin Martin, 1915-2006
Object Type: Report
System: The UNT Digital Library
Determination on Neutron Density With Bismuth Foils : Final Report - Problem Assignment 131 - X21P (open access)

Determination on Neutron Density With Bismuth Foils : Final Report - Problem Assignment 131 - X21P

It is usual to determine the density of neutrons by using foils of metals which become radioactive as a result of bombardment in the region under investigation. From the rate of disintegration of the newly formed radioactive element the number of neutrons absorbed can be calculated. By use of the capture cross section of the element of which the foil is composed the density of the neutrons can then be computed. By counting the alpha particles from a bismuth foil of known weight after exposure to neutrons the density of the neutrons which produced this activity can be calculated. The least accurately known value which enters into this evaluation is the capture cross-section of bismuth for pile neutrons. This value may be improved by future measurements. It is of importance only for absolute measurements of neutron density so that relative values can be measured with considerable accuracy on the basis of known data.
Date: May 30, 1944
Creator: Curtiss, Leon Francis, 1895-
Object Type: Report
System: The UNT Digital Library
Physico-chemical Studies of U-Compounds in Solution : Progress Report, February 1945 (open access)

Physico-chemical Studies of U-Compounds in Solution : Progress Report, February 1945

This progress report discusses progress on oxidation-reduction studies, including polarography, as well as the Uranium-complex formation including electrical transport and spectro-photometric work. This report covers the work done in the period of February of 1945.
Date: May 26, 1948
Creator: Tishkoff, G. H. & Fanta, Paul E.
Object Type: Report
System: The UNT Digital Library
Preliminary Report on the Hydrolytic Behavior of Cerium (IV) (open access)

Preliminary Report on the Hydrolytic Behavior of Cerium (IV)

The following report analyzes the hydrolytic behavior of cerium and compares them with the actinides of uranium and plutonium.
Date: May 25, 1948
Creator: Kraus, K. A.; Holmberg, R. W. & Nelson, F.
Object Type: Report
System: The UNT Digital Library
The Deposition of Plutonium and Certain Fission Products in Bone as a Decontamination Problem (open access)

The Deposition of Plutonium and Certain Fission Products in Bone as a Decontamination Problem

The following report discusses the deposition of radioactive elements during a nuclear fission in the skeleton. Studies are concerned with chronic effects of toxic radiation developing within the bone marrow and decontaminating the cells.
Date: May 15, 1946
Creator: Copp, D. Harold; Greenberg, David M. & Hamilton, Joseph G.
Object Type: Report
System: The UNT Digital Library
The Tracer Chemistry of Americium and Curium in Aqueous Solutions (open access)

The Tracer Chemistry of Americium and Curium in Aqueous Solutions

The following report presents data and conclusions from investigations of the chemical properties of elements 95 (americium, Am) and 96 (curium, Cu) by means of tracer techniques.
Date: May 1948
Creator: Thompson, Stanley Gerald, 1912-1976; Morgan, L. O.; James, R. A. & Perlman, Isadore
Object Type: Report
System: The UNT Digital Library
The Ratio of Amino Acid Nitrogen to Creatinine in the Urine as a Sensitive Test for Uranium Poisoning (open access)

The Ratio of Amino Acid Nitrogen to Creatinine in the Urine as a Sensitive Test for Uranium Poisoning

Report discussing experiments that were performed to determine whether amino acids in urine could be used as a test of subtle uranium poisoning.
Date: May 25, 1948
Creator: Berke, Harry & Rothstein, A.
Object Type: Report
System: The UNT Digital Library
The Coprecipitation of Thorium and Uranium Peroxides (open access)

The Coprecipitation of Thorium and Uranium Peroxides

From abstract: "Experiments covering the coprecipitation of Thorium and Uranium peroxides are described on synthetic and actual 1300 cycle machine wash effluents."
Date: May 10, 1946
Creator: Oringer, Roy; Woodard, R. W. & Larson, C. E.
Object Type: Report
System: The UNT Digital Library
An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases (open access)

An Ion Chamber for the Determination of Small Amounts of Tritium in Other Gases

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.
Date: May 5, 1951
Creator: Mattraw, H. C.
Object Type: Report
System: The UNT Digital Library
Stabilizer for Temperature Control Equipment (open access)

Stabilizer for Temperature Control Equipment

From abstract: "A simple electronic circuit is described, the use of which greatly improves the temperature regulations obtainable with Beta equipment. The circuit utilizes the time derivative of the temperature to counteract oscillation and overshoot. No other changes are required in existing equipment for installation of the stabilizer."
Date: May 14, 1945
Creator: Macleish, K. G. & Palmer, R. C.
Object Type: Report
System: The UNT Digital Library
Scale-Up of Alternate HRT Core (open access)

Scale-Up of Alternate HRT Core

"In order to determine the factors involved in the scale-up of cores with concentric inlet and outlet pipes, a 48 inch carbon steel flow model, geometrically similar to a 6 foot diameter core, has been assembled and tested...Visual studies were made of dye and gas behavior in the sphere, and quantitative measurements of point residence times were obtained through the use of conductivity cells actuating a Brush recorder. Static pressure drop across the core was measured."
Date: May 7, 1954
Creator: Lesem, L. B. & Harley, P. H.
Object Type: Report
System: The UNT Digital Library