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
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
Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962 (open access)

Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962 (open access)

Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 15, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961 (open access)

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
System: The UNT Digital Library
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964 (open access)

Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date: July 15, 1964
Creator: Howard, C. L.
System: The UNT Digital Library
Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program (open access)

Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program

Results of processing 47 metric tons of Brookhaven spent reactor fuel are summarized.
Date: December 15, 1960
Creator: McDuffee, W. T.
System: The UNT Digital Library
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C (open access)

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
System: The UNT Digital Library