The X-Ray Spectra of Polonium Atomic Number 84 (open access)

The X-Ray Spectra of Polonium Atomic Number 84

From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley's law and with those claimed by Hulubei. Decay of polonium-210 (half life = 138 days) and growth of lead-206 (stable) were observed over a period of 180 days."
Date: April 15, 1952
Creator: Peed, W. F.; Burkhart, L. E.; Staniforth, R. A. & Fauble, L. G.
System: The UNT Digital Library
The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction (open access)

The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction

From abstract: "The reaction between hydrogen and oxygen with the aid of various catalysts (especially platinum on aluminua) has been studied, and the operating variables such as flow rates, space velocity, temperature, and gas composition have been examined rather extensively. It has been found that hydrogen and oxygen in stoichiometric proportions and mixed with either steam or helium may be made to react to the extent of 99.5% or greater at space velocities up to 30,000 hr-1, or even higher, at temperatures from 100[degrees] to 900[degrees]C, and with mixtures ranging from less than 1% hydrogen to mixtures containing 12% hydrogen and 6% oxygen. Richer mixtures, including undiluted electrolytic gas (H2 + 1/2 O2) have been used with catalysts less active than platinum (e.g. copper, silver, nickel and V2O5) but here the gas mixture is explosive and care must be taken to prevent explosions. The thermal reaction between hydrogen and oxygen diluted with steam has also been investigated at temperatures between 500[degrees] and 800[degrees]C."
Date: January 15, 1952
Creator: Kuhn, D. W.; Ryon, A. D.; Palko, A. A. & Clewett, G. H.
System: The UNT Digital Library
Determination of Oxygen in Oxide Films by Neutron Activation Analysis (open access)

Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities masked F18 in the aluminum. It is concluded that a 1 A (0.01 μgm/cm^2) oxide film thickness may be measured by a neutron irradiation at a flux of 10^14 n/cm^2/sec but chemical separation of induced radioactivity from the bulk metal is essential.
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
System: The UNT Digital Library
Containment Properties of DCX (open access)

Containment Properties of DCX

The "absolute" containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confinement in space and momentum are plotted for 300 Kev deuterons.
Date: June 15, 1959
Creator: Fowler, T. K. & Rankin, M.
System: The UNT Digital Library
The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process (open access)

The Effect of Acidity and Reducing Agents on Ruthenium Solvent Extraction by Tributyl Phosphate in the 25 Process

Results of tracer studies suggest that, in tributyl phosphate extraction processes designed to recover and purify fissionable material, minimum ruthenium extraction should be obtained from feeds at least 2 M in nitric acid or at least 1 M acid-deficient. Ruthenium decontamination was decreased by preheating the feed and increased by pretreatment with reducing agents. A pretreatment using 0.06 M ferrous ion and 0.5 M urea with 1 hr simmering at 85°C should increase ruthenium decontamination about 10-fold in the 25 process. If other process considerations dictate the use of a low-acid feed, decontamination from ruthenium may be improved by using 3 M nitric acid as the scrubbing solution. Apparently, the scrubbing process is quite time-dependent; a solvent holdup time of about 15 min may be needed in the scrub section for maximum decontamination.
Date: December 15, 1954
Creator: Flanary, J. R. & Frashier, L. D.
System: The UNT Digital Library
Electromagnetic Research Division Quarterly Progress Report: Part I for Period Ending December 31, 1951 (open access)

Electromagnetic Research Division Quarterly Progress Report: Part I for Period Ending December 31, 1951

From abstract: "Operation of the 86-inch cyclotron has been continuous except for a three-day interruption caused by a water leak inside the vacuum chamber; monthly output has averaged over 210,000 [mu]a-hr; the average continuous (168-hour week) beam power has been approximately 5.5 kw; and the energy of the beam has been determined to be ~19.4 Mev. No changes due to radiation damage have been detected in Inconel tubes containing UF4-NaF-KF eutectic which were irradited in the 96-inch cyclotron with power inputs up to ~415 watts/cc. The major components of the 63-inch cyclotron have been fabricated and are being tested as the machine is being assembled. On the 22-inch cyclotron a radius-wise examination of the fine structure of the proton beam reveals definite proton orbits. Several grams of very pure uranium 235 have been prepared; the chemical recovery for first-stage separation of U 236 has been established as 97%; and facilities for laboratory-scale separation of plutonium isotopes are being prepared."
Date: January 15, 1952
Creator: Livingston, Robert S. & Howard, F. T.
System: The UNT Digital Library
The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores (open access)

The Effect of X Irradiation in Oxygen and in Hydrogen at Normal and Positive Pressures on Chromosome Aberration Frequency in Tradescantia Microspores

Effect of x irradiation in oxygen and in hydrogen on chromosome aberration frequency in tradescantia microspores.
Date: September 15, 1950
Creator: Giles, Norman H., Jr. & Beatty, Alvin V.
System: The UNT Digital Library
Neutron Physics Division Annual Progress Report, September 1, 1958 (open access)

Neutron Physics Division Annual Progress Report, September 1, 1958

Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.
Date: February 15, 1958
Creator: Oak Ridge National Laboratory. Neutron Physics Division.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1957-January 1958 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1957-January 1958

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.
Date: February 15, 1958
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field (open access)

Some Experiments Relating Ion Diffusion in a Plasma to the Neutral Gas Density in the Presence of a Magnetic Field

In some recent experiments the ion density in a plasma was measured as a function of radial distance from a d-c arc source of ions for the magnetic field intensities from 2500 to 14000 oersted. The diffusion coefficient appeared to very inversely as the square of the magnetic field strength, D~1/H2. The absolute value of D was shown to be approximately that which would be predicted by the collision diffusion theory when account is taken of the shorting effect of the end walls. The purpose of this report is to continue the examination of ion diffusion in a plasma and field experimentally the relation between the diffusion coefficient and the neutral gas pressure for a constant magnetic field.
Date: June 15, 1956
Creator: Reidigh, Rodger V.
System: The UNT Digital Library
Disassembly and Postoperative Examination of the Aircraft Reactor Experiment (open access)

Disassembly and Postoperative Examination of the Aircraft Reactor Experiment

The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much of the planned hot-cell inspection was postponed and complete examination of all but a few specimens was indefinitely suspended. The few examinations that were completed are described in this report, along with a description of the disassembly of the ARE system. Diagrams of the fuel system, sodium system, and off-gas system are presented in Figs. 1, 2, and 3 for reference use in visualizing the disassembly process.
Date: April 15, 1958
Creator: Cottrell, W. B.; Crabtree, T. E.; Davis, A. L. & Piper, W. G.
System: The UNT Digital Library
Examination of 6" Diameter "O" Ring from HRT Mockup. Metallography Report (Y-12) No. 39 (open access)

Examination of 6" Diameter "O" Ring from HRT Mockup. Metallography Report (Y-12) No. 39

A six-inch diameter "O" ring from the HRT Mockup was examined metallographically after 2452 hours exposure to uranyl sulfate solution at 300C. surface defects, except for cold work defects were found only in areas exposed to uranyl sulfates. Defects found were pits, transgranular cracks, surface cracks, and grain attacks.
Date: January 15, 1957
Creator: Kegley, T. M., Jr.
System: The UNT Digital Library
Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys (open access)

Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys

It has been reported in the literature that prolonged soaking of 16 wt & uranium-aluminum alloys at elevated temperatures induces a microstructural changed termed "conglobulation". this process is essentially a spheroidization of the UAl4 eutectic. Conclusions of the tests: (1) Extended soaking of 48 wt $ uranium-aluminum alloy billets at 600 C does not improve their hot-rolling characteristics. (2) Soaking periods of 50 hours and greater reduce the tensile and yield strengths of these alloys. (3) Soaking for 50 hours results in complete spheroidization of the eutectic in 48 wt % uranium-aluminum alloys.
Date: March 15, 1957
Creator: Thurber, William C.
System: The UNT Digital Library