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Making Music Accessible in the UNT Digital Libraries

Description: This report documents the "Making Music Accessible in the UNT Digital Libraries" project funded by the Dean's Innovation Grant. The final report briefly describes the project purpose, activities, budget, outcomes, best practices, and program continuity.
Date: September 21, 2021
Creator: Hicks, William & Cleveland, Susannah, 1972-
Partner: UNT Libraries
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[School/Museum/University Collaboration Project report]

Description: A report titled 'School/Museum/University Collaboration Project', submitted to the Edward and Betty Marcus Foundation by D. Jack Davis and R. William McCarter.
Date: September 20, 1994
Creator: Davis, D. Jack & McCarter, R. William
Partner: UNT Libraries Special Collections
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A Physical Property Summary for Fluoride Mixtures

Description: This report presents a summary of certain physical properties that have been determined experimentally on the fluoride mixture that have been formulated at ORNL (Rers. 1, 2). These properties include the density, enthalpy, heat capacity, heat of fusion, thermal conductivity, viscosity, Prandtl number, electrical conductivity and surface tension. In addition to the experimental data, values have been predicted for the heat capacity and density of the other mixtures from the correlations of these properties. Estimates of the viscosity have also been made for a number of the mixtures on which no experimental data were available.
Date: September 5, 1956
Creator: Cohen, S. I.; Povers, W. D. & Greene, N. D.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Secret Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, production of fuels, compatibility of materials at high temperatures, chemistry, analytical chemistry, metallurgy, dynamic corrosion studies, general corrosion studies, fabrication research, welding and brazing investigations, mechanical properties studies, ceramic research, nondestructive testing studies, heat transfer and physical properties, radiation damage, fuel recovery and reprocessing, critical experiments.
Date: September 4, 1956
Creator: Jordan, W. H.; Cromer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, production of fuels, compatibility of materials at high temperatures, chemistry, analytical chemistry, metallurgy, dynamic corrosion studies, general corrosion studies, fabrication research, welding and brazing investigations, mechanical properties studies, ceramic research, nondestructive testing studies, heat transfer and physical properties, radiation damage, fuel recovery and reprocessing, critical experiments.
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
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Operation of the ORNL Graphite Reactor and the Low-Intensity Test Reactor — 1955 LITR Flux Traverses

Description: The ORNL Graphite Reactor operated very well during 1955. The downtime was low, only 8.6%. The fuel in the bonded slugs did not perform as well in 1955 as in 1954. Much of the trouble was undoubtedly due to growth of slugs which were not beta-transformed. It is known that some slugs had grown over 1/2 in. The automatic central system installed in 1954 continued to operate satisfactorily. The cooling system gave minor trouble when one of the 900-hp fan meters had to be replaced because of shorts in the rotor. The high radiation in the canal was the largest source of trouble. Approximately 55 tons of slugs discharged from the reactor in 1952 was sent to the Metal Recovery Plant. Enough slugs had raptured, due to their long exposure in the canal and reactor, to badly contaminate of water. Most of the contamination was removed by the end of the year, but the radioactivity which had soaked into the canal wells was enough to give high radiation fields. A solution to this problem was being sought at the end of the year. A study is under way on the possibility of increasing the flux of the ORNL Graphite Reactor by reloading with enriched uranium fuel. Results of the study appear to be promising.
Date: September 10, 1956
Creator: Rupp, A. F. & Cox, J. A.
Partner: UNT Libraries Government Documents Department
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The Influence of End Mirrors, High Density and Long Tube Length on Radial Diffusion

Description: Diffusion in an arc plasma across a magnetic field is investigated. The geometry is similar to that reported in ORNL-1890 but with the addition of magnetic mirrors on the ends of the arc chamber. It is shown that mirrors do not eliminate the "short circuit" effect. Comparison of the e-folding length, rₒ, of the radial ion density with and without mirrors, affords a direct measurement of ℓ/λ where ℓ is the arc length and λ the mean-free-path. In addition rₒ is independent of gas pressure with mirrors and varies as √p without mirrors. The condition for the elimination of the "short circuit" effect is discussed, as well as the case in which the "short circuit" is still present but the ions diffuse (rather than stream) to the end walls. In this case rₒ is directly proportional to the gas pressure. These effects are compared to some experimental results of Neidigh
Date: September 22, 1955
Creator: Simon, Albert
Partner: UNT Libraries Government Documents Department
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ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

Description: This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after irradiation and after decay of the protactinium 233 was greater than before irradiation. A fuel element of this nature appears to offer excellent potentialities from the standpoint of radiation stability.
Date: September 7, 1955
Creator: Carrell, R. M.
Partner: UNT Libraries Government Documents Department
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Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)

Description: The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange resin and titration of the liberated acid with standard alkali solution. Recommendations are made regarding the preferred methods of determining the constituents in dibasic aluminum nitrate and regarding means of minimizing errors in these analyses.
Date: September 16, 1955
Creator: Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogenous Reactor Fuel II. Polarographic Determination of Chromium

Description: A satisfactory ion-exchange-polarographic method was developed for the determination of either chromium(VI) or total chromium in Homogeneous Reactor fuels. Total chromium is determined as chromium (VI) , i.e., chromate, and in the same way as is chromium(VI), after chromium in the lower valence states is oxidized to chromate by potassium permanganate. Chromate is separated from all interfering metal ions in the fuel by ion exchange on a Dowex 50 resin column. The Chromate in the effluent is determined polarographically in approximately 0.75 M sodium hydroxide solution as supporting electrolyte. A well polarographic wave is obtained for the chromium (VI) chromium (III) reduction at a half-wave potential of -0.85 volt vs. the S.C.E. The relative standard deviation of the data for 2 μg of chromium (VI) per ml was 2%; for 4 μg of total chromium per ml, it was 3%. An ion-exchange-polarographic method was developed also for the determination of chromium(III). Chromium (III) is separated from all interfering ions in the fuel by ion exchange on a Dowex 1 resin column. The chromium (III) in the effluent is determined polarographically in a 1M ammonia-1M ammonium chloride supporting electrolyte. The wave obtained at a half-wave potential of -1.42 volt vs. the S.C.E is poorly defined, and the method is not entirely satisfactory.
Date: September 13, 1955
Creator: Horton, A. D. & Thomason, P. F.
Partner: UNT Libraries Government Documents Department
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Absorption and Turnover Rates of Iron Measured by the Whole Body Counter

Description: Human iron metabolism has been extensively studied in the past twenty-five years with the radioisotopes iron⁵⁵ and iron⁵⁹. Before the availability of the whole body counter, however, iron absorption studies were performed by the indirect methods of fecal assay of unabsorbed radioiron, and estimation of red cell incorporation of absorbed tracer. The few long-term excretion studies performed required numerous assumptions, since human iron excretion was less well understood. Whole body counting provides a simple and accurate method of measuring the total body retention of administrative tracer iron⁵⁹, thus making absorption and subsequent excretion determinations possible with a single radioiron study. The energetic gamma emissions of iron⁵⁹ permit ready external detection with small quantities of isotope, Normal radioiron distribution is uniform throughout the circulating red cell mass and thus minimize geometry influences on the counting efficiency, 0nly the 45.1 day half-life of iron⁵⁹ limits long term iron turnover studies. Measurements of iron⁵⁹ absorption and long-term body turnover have been under way at Brookhaven National Laboratory for over two years. The present paper outlines some of the results of these studies, and discusses some implications of the method.
Date: September 5, 1962
Creator: Price, D. C.; Cohn, S. H. & Cronkite, B. P.
Partner: UNT Libraries Government Documents Department
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The Influence of Radiation-Produced Defects on the Precipitation of Carbon in Iron

Description: Iron containing approximately 0.01 wt. % carbon was quenched from 700°C and irradiated in the BNL reactor at 57°C for various lengths of time. The rate of decay of the Snoek internal friction peak was observed at 57°C after irradiation. After a 4-hour irradiation the rate of decay of the peak was one order of magnitude faster than the rate of decay in an unirradiated specimen. Longer irradiation times up to 48 hours caused no further acceleration of the decay rate. This observation implies that in the irradiated specimens there are ten times more precipitation nuclei than in the unirradiated specimens. This is confirmed by electron microscope studies which also show a factor of ten greater concentration of precipitate particles in specimens irradiated for 5 hours at 57°C as compared to an equivalent unirradiated specimen. Electron microscope studies also show that longer irradiation times do not increase further this number of precipitates. Although these experiments clearly demonstrate the enhancement of nucleation by neutron irradiation, it is not known why the incipient nuclei created by irradiation times of longer than 5 hours do not form observable precipitate particles.
Date: September 6, 1962
Creator: Fujita, F. E. & Damask, A. C.
Partner: UNT Libraries Government Documents Department
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Computer Information Center

Description: The purpose of the Computer Information Center is to stimulate the production of documentation and to make it readily available to computer users within the Laboratory. In addition, the Center will endeavor to obtain all publications of programming and machine manuals pertinent to LRL.For the Computer Information Center to be effective, it is essential that its coverage be as complete as possible. Computer users who have written programs or subroutines are therefore urged to submit write-ups for publication to Chet McIntosh (Bldg. 161 - Room 1241) or Nora Kegel (Bldg. 161 - Room 1239). All materials presented will be edited and the final draft returned to the author for verification prior to publication within the Laboratory.
Date: September 1963
Partner: UNT Libraries Government Documents Department
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Future Program for the Cern PS and the Brookhaven AGS

Description: The alternating-gradient proton synchrotrons at CERN and Brookhaven are very similar in size, design and in their experimental use. For this reason, collaboration between the groups at CERN and Brookhaven has been close throughout the history of these two machines. For the most part this has taken the form of exchanges of visits of individual machine designers and of high-energy physicists. By 1962, however, it appeared that the reciprocal flow of information was not adequate and a more formal meeting was arranged. This meeting took place at Brookhaven during the week of September 10, 1962. CERN sent a representative group of machine physicists and high-energy physicists. The meeting was attended also by observers from several American high-energy installations. The discussion covered a wide range of topics, from operating characteristics of the machines themselves to future trends in design of experimental equipment. Plans for beam ejection were presented, techniques were described for better use of secondary beams from internal targets, progress was summarized on dc and rf particle separators. and future trends in neutrino experimentation were predicted.
Date: 1962-09-10/1962-09-14
Creator: Blewett, J. P.; Bittner, J. W.; Brown, H. N. & Maschke, A. W.
Partner: UNT Libraries Government Documents Department
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A Sublimation Pump

Description: During a visit to Professor H.G. Harb at the University of Wisconsin, it was apparent that he had succeeded in obtaining fresh, clean chemisorptive layers of titanium by sublimation and chat that this could be adapted into an effective high vacuum pump. Two previous techniques of obtaining a chemisorptive layer of titanium, namely catholic sputtering and evaporation from the liquid droplet, have been extensively investigated and reported. Each of these seem to have inherent difficulties in stability and continuity of operation that appear to be eliminated or effectively reduced by the sublimation procedure. A development program was started at Brookhaven National Laboratory to investigate the possibilities of each sublimation of titanium as opposed to evaporation from the liquid.
Date: September 20, 1962
Creator: Gould, C. L. & Mandel, P.
Partner: UNT Libraries Government Documents Department
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[Certificate of liability insurance for LSR dated 9/9/2011]

Description: A certificate of liability insurance dated September 9, 2011, for Lone Star Ride Fighting AIDS. The document details the insurance purchased by LSR for the event and lists them as general liability, automobile insurance for both hired and non-owned autos with a limit of $500,00, and accident health insurance per claim. The certificate is to be held by the city of Fort Worth.
Date: September 9, 2011
Creator: Steven Graves Insurance Agency
Partner: UNT Libraries Special Collections
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[Certificate of liability insurance for LSR dated 9/9/2011, 2]

Description: A certificate of liability insurance dated September 9, 2011, for Lone Star Ride Fighting AIDS. The document details the insurance purchased by LSR for the event and lists them as general liability, automobile insurance for both hired and non-owned autos with a limit of $500,00, and accident health insurance per claim. The certificate is to be held by the city of Fort Worth.
Date: September 9, 2011
Creator: Steven Graves Insurance Agency
Partner: UNT Libraries Special Collections
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Flexibility of a Tube in Which Slugs Slide

Description: An approximate calculation is made of the variations of the flexibility of a long cartridge with the length of the slug used, assuming that the jacket slides without friction.
Date: September 13, 1944
Creator: Young, G.
Partner: UNT Libraries Government Documents Department
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