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ST JOHN'S Cemetery: A report detailing how Denton County Commissioner Hub Clark stole a cemetery from a Pilot Point freedpersons community in 1938.

Description: This report was submitted to the Denton County Commissioner’s Court on December 12, 2023. The independent research contained herein was inspired by a collaborative community effort to highlight the emerging historical narrative of the St. John's freed-persons community of Pilot Point, its unexplained disappearance in the 1930s, and the events that led to the community's cemetery becoming landlocked and inaccessible to the public for more than eighty years.
Date: December 12, 2023
Creator: Luther Rummel, Jessica
Partner: UNT College of Arts and Sciences
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Operation Pre-Gnome: Seismic Data from Natural Phenomena and High-Explosive Tests Near Carlsbad, New Mexico

Description: Formulas derived from earlier work satisfactorily predicted low frequency ground effects resulting from the Pre-Gnome explosions, but they not predict high accelerations associated with high frequency ground waves. The Pre-Gnome experiments taken since indicated that accelerations and ground amplitudes are proportional to the explosive charge, but physical conditions limit extrapolation on this basis to relatively low yields. Predicted accelerations resulting from the 10 kt Gnome explosion in p… more
Date: January 12, 1960
Creator: Carder, Dean S.; Murphy, L. M.; Cloud, W. K. & Pearce, T. H.
Partner: UNT Libraries Government Documents Department
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Free Convection in the SIR Mark A Rotating Plugs

Description: This technical report is intended as a brief description of the free convection problem existing in the various annuli of the SIR Mark A rotating plugs. It is by no means a complete report of the plug "hot tests", but merely records some of the more significant experimental observations and presents a few of the theories and calculations made to explain the observed free convection phenomenon. The general discussion which follows is chronological. Details of analyses are relegated to the Appen… more
Date: November 12, 1953
Creator: Timo, D. P.
Partner: UNT Libraries Government Documents Department
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Use of Convergent and Asymptotic Series for Computation of the Modified Bessel Function of the First Kind.

Description: In the Communications of the ACM of April, 1960, p. 240, there appeared two Algol algorithms for the computation of In, the modified Bessel function of the first kind. One of these algorithms uses a convergent series and the other an asymptotic series. Their author, Dorothea S. Clarke, did not give any information with regard to which algorithm is more appropriate in a given situation (a given situation meaning the computation of In (x) for a definite pair of numbers n and x). Such information … more
Date: December 12, 1960
Creator: Bumgarner, L. L.
Partner: UNT Libraries Government Documents Department
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Design and Development of a High-Temperature High-Pressure Spectrophotometer System: Status Report

Description: On 3/14/60 the Applied Physics Corporation was awarded a subcontract for the design and development of a high-temperature high-pressure spectrophotometer system based on the Cary Model 14pm Spectrophotometer insofar as possible, and consistent with our specifications, No. CTD-2, December 16, 1959.
Date: November 12, 1960
Creator: Biggers, R. E. & Wymer, R. G.
Partner: UNT Libraries Government Documents Department
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Secondary-Side Water Treatment for Corrosion Control in Aluminum Heat Exchangers: Practices and Results at the Oak Ride Research Reactor

Description: Standard water treatment practices have proven adequate for scale and corrosion control on the secondary side of the ORR pool-cooling heat exchanger. Corrosion rates measured on specimens exposed to secondary water showed maximum corrosion rates of approximately 1 mpy during the first exposure period and these rates decreased during subsequent exposure.
Date: August 12, 1959
Creator: P. D. Neumann
Partner: UNT Libraries Government Documents Department
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A Method for Determining the Optimum Dimensional Parameters of a Scalloped Channel so as to Minimize Fuel-Element Bowing in a Septafoil Arrangement

Description: The use of a scalloped cross-sectional coolant channel has been suggested as possible solution of the fuel-element bowing problem inherent in the septafoil type of geometry. Using simplified assumptions, a method has been developed for calculating the rod spacing and scallop size necessary to produce equal average fuel-element surface temperatures in the central and peripheral regions of the coolant flow channel at the mid-section of each fuel-rod cluster under a given set of reactor flow condi… more
Date: June 12, 1959
Creator: Wantland, J. L. & Kidd, G.J. Jr.
Partner: UNT Libraries Government Documents Department
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Neutron and Gamma-Ray Attenuation for a Fission Source in Water : Comparison of Theory with LTSF Measurements

Description: Calculations are presented of the fast neutron dose rate, the gamma-ray dose rate, and the thermal neutron flux along the source plate axis in the Lid Tank with the tank filled entirely with water. These calculations are compared with experimental measurements. The calculations are absolute and are compared with absolute measurements.
Date: March 12, 1957
Creator: Otis, David Ridgway
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of Beryllium : Literature Survey

Description: Lewis in 1929 determined the thermal conductivity of beryllium metal for the first time. The next measurement reported in the open literature on the thermal conductivity of beryllium was by Powell in 1953. Measurements were also made by Grenell, Linebrink, and Johnson at Battelle Memorial Institute in 1947. Their values are in good agreement with those of Powell.
Date: February 12, 1957
Creator: Powers, W. D.
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Second Quarterly Progress Report May 12-August 12, 1962

Description: This is the second quarterly report on the work done under Contract AT(04-3)-189, Project Agreement No. 27. The results reported here have to do primarily with the loss in a rectangular (1/2" x 1-3/4") channel in the horizontal orientation, without contraction-expansion inserts.
Date: September 12, 1962
Creator: Janssen, E. & Kervinen, J. A.
Partner: UNT Libraries Government Documents Department
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Resonance Integral Calculations for Evaluation of Doppler Coefficients: The Rapture Code

Description: A code (RAPTURE) was programmed for the Philco TRANSAC 2000 computer to perform calculations needed for the evaluation of Doppler Coefficients in fast reactors with degraded neuron spectra. This code computes resonance integrals, averages them over resonance parameter distributions, and computes fission and capture cross sections as a function of fuel temperature and of potential scattering cross section per absorber isotope.
Date: June 12, 1962
Creator: Ferziger, Joel H.; Greebler, P.; Kelley, M. D. & Walton, J. W.
Partner: UNT Libraries Government Documents Department
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Progress Report on the Flotation of Uranium Bearing Minerals From Lake Athabaska Ore, Sample 43-1

Description: At the request of the Atomic Energy Commission, a 456 pound sample of Lake Athabaska ore was shipped to this laboratory by the Radioactivity Division of the Canadian Bureau of Mines. The sample was received on March 10, 1952 and given our number 43-1. Several series of flotation tests were performed on the sample.
Date: October 12, 1953
Creator: Breymann, John B.; Charles, W. D. & Thomas, P. N.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1955

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research. The ANP Project is comprised of about 530 technical and scientific personnel engaged in many phases of rese… more
Date: March 12, 1956
Creator: Jordan, W. H.; Cremer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Laboratory Development of the Thorex Process

Description: Changes made in the Thorex process flowsheet were a decrease in the extraction column acidity to decrease thorium losses and the addition of a second thorium solvent-extraction cycle to provide the increased decontamination required when thorium irradiated to 2000-4000 g of U233 per ton is processed. Bonded slugs could not be dissolved by the Thorex flowsheet procedure. Various laboratory scale studies on feed preparation, first-cycle variables, and radiation damage to the solvent are reported.
Date: June 12, 1956
Creator: Wischow, R. P. & Mansfield, R. G.
Partner: UNT Libraries Government Documents Department
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Biology Progress Report for Period Ending August 15, 1955

Description: Progress report of the Oak Ridge National Laboratory Biology Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the division and departmental activities in: cytology and genetics, microbial protection and recovery, mammalian recovery, mammalian genetics and development, pathology and physiology, microbiology, biochemistry, enzymology and photosynthesis, plant biochemistry, general physiology, and biophysics.
Date: December 12, 1955
Creator: Hollaender, Alexander; Carson, Stanley F. & Sleughter, E. J.
Partner: UNT Libraries Government Documents Department
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Dissolution of Metals in Fused Fluorides

Description: In scouting tests, a number of metals used in nuclear reactor fuel elements were dissolved by 44.5-48.5-7.0 mole % ZrF4-KF-NaF fused salt at 675°C through which HF was being passed. These included type 304 stainless steel at 4 mils/hr; type 347Nb stainless steel at 7 mils/hr; thorium at 14 mils/hr; nonirradiated uranium at 17 mils/hr; zirconium at 22-35 mils/hr; titanium at 31 mils/hr; and Zircaloy-2 at 22-46 mils/hr. Only small amounts of volatile fission products formed when irradiated uraniu… more
Date: October 12, 1953
Creator: Leuze, R. E.; Cathers, G. I. & Schilling, C. E.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Partner: UNT Libraries Government Documents Department
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Plutonium Oxide- Plastic Mixtures for Critical Mass Studies

Description: Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date: May 12, 1960
Creator: Crocker, H. W.
Partner: UNT Libraries Government Documents Department
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PRTR Calandria Fabrication Report

Description: The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and li… more
Date: July 12, 1960
Creator: Pedersen, L. T. & Kreiter, M. R.
Partner: UNT Libraries Government Documents Department
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Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
Partner: UNT Libraries Government Documents Department
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