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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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An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

Description: The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed by the designs themselves, the high operating temperatures involved require the careful selection of materials and joining techniques. The choice of fabrication procedure for a given component must not only be based upon the stresses and temperatures to be encountered, but also upon special factors peculiar to nuclear service. Since many reactor applications employ highly corrosive environments, compatibility of the structural ma terials with the corrosive media is of paramount importance. The low nuclear cross-section require ment for brazing alloys to be used inside the re actor also places stringent limitations on the possible choices of in-pile applications. The use of boron in alloys for certain service may not be considered feasible, for example, because of its high nuclear absorption cross section. Although welding is used extensively in the construction of radiators and heat exchangers, high-temperature brazing is also attractive for several applications. In Fig. 1, a photograph of a liquid-metal-to-air radiator, it can be seen that brazing serves as the most feasible method of attaching cooling fins to thin-walled tubes. Typical of the joints obtainable is that shown in Fig. 2, in which are shown stainless-steel-clad-copper high-conductivity fins2 brazed to an Inconel tube.
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J.P.
Partner: UNT Libraries Government Documents Department
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The Oak Ridge National Laboratory Research Reactor Safeguard Report

Description: The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of demineralized water. The reactor tanks are submerged in a barytes concrete pool, filled with water, which serves as a biological shield. Experimental facilities include two 18" diameter "Engineering Test Facilities" and six 6" diameter beam holes. In addition, access to the core is available through the water of the pool. The result on the surrounding population of release to the atmosphere of a large fraction of the radioactive material in the core has been computed by two methods. It is shown that under certain conditions off-area personnel could be subjected to greater than the maximum permissible exposure. An analysis of the maximum hazard caused by the release of the entire contents of the core to the local watershed indicates that the resulting incident could be quite serious, but with proper monitoring and supervision would probably not constitute a lethal hazard. The probability of the occurrence of a catastrophic release of activity of sufficient magnitude to cause widespread hazard to life is quite small and it is believed that the measures taken to lessen this probability are adequate. An Appendix, Volume II, contains supporting information for this report, and is also intended to serve as a reference for future use.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
Partner: UNT Libraries Government Documents Department
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Remarks on the Double Dispersion Approach to the Bethe-Salpeter Equation

Description: The following remarks are made on the applicability of the double dispersion approach to the Beth-Salpeter equation introduced previously. 1) Any invariant solution of the Bethe-Salpeter equation in ladder approximation satisfies the double dispersion representation when the total energy-momentum is space-lake. 2) There are some exceptional invariant solutions which are not given by the previous method in the equal-mass case, but the existence of such solutions is very unlikely in the unequal-mass case. 3) In the case of the general separated kernel the previous results give the correct solutions even if the kernel does not reproduce the double dispersion representation.
Date: August 7, 1962
Creator: Nakanishi, Noboru
Partner: UNT Libraries Government Documents Department
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Theoretical Study of a Source of Intermediate Energy Neutrons

Description: Abstract. An analysis is made of a proposal to obtain neutrons of 15-25 Kev energy by moderating fast neutrons in aluminum and then reflecting off titanium. The fluxes calculated do not significantly exceed those obtainable from a standard antimony-beryllium photoneutron source. Two appendices treat aspects of the transport of neutrons through a slab of finite thickness.
Date: January 7, 1954
Creator: Bludman, Sidney A.
Partner: UNT Libraries Government Documents Department
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Radiation Effects on Cell Renewal Systems

Description: Much of the early work in radiation biology was predicted on the assumption that radiation effects could be understood in terms of a single mechanism. This "single mechanism" was studied on appropriate biological test objects that could be developed into biological dosimeters. Attempts were made to assess the properties of "the" biological effects from the relations of "biological dose" (skin dose, bean dose, fly dose, etc.) to physical parameters of irradiation. Notwithstanding the rigidity of this approach, some useful generalizations emerged. During the past 20 years or so, it has become increasingly obvious that ionizing radiations may affect living systems in different ways, and that what is true in one cell, tissue, or species and in one set of circumstances does not necessarily apply to another situation. Accordingly, the search for a single mechanism was replaced by dedicated application to specific detail. In consequence, we now know a great deal about the fine structure of some radiation effects, and there is once again a tendency to formulate generalizations. This paper will attempt to analyze the mechanism of a well-defined syndrome that arises in certain cell systems after a single dose of ionizing radiation. Our attention will be directed mainly to those systems in which cell production and loss are in dynamic equilibrium.
Date: December 7, 1962
Creator: Patt, Harvey M. & Quastler, Henry
Partner: UNT Libraries Government Documents Department
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Some Specific Considerations of the Potential Hazards of Heavy Primary Cosmic Rays

Description: The radiation of the Van Allen belts and the solar flares consists primarily of electrons and protons, the biological effects of which are reasonably well known. However, there is a very small component of the galactic cosmic rays which consists of stripped atomic nuclei of atoms as heavy as iron. The biological effects of such particles have not been extensively investigated because it is impossible to produce them in the laboratory with an energy high enough to use for mammalian experiments. Consequently it has been necessary to approach the problem by indirect methods.
Date: December 7, 1962
Creator: Curtis, Howard J.
Partner: UNT Libraries Government Documents Department
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Plant Fructose-1,6-Diphosphatases

Description: Several important metabolic processes in plants involve the conversion of triose phosphate to hexose monophosphate. These include the synthesis of carbohydrates from precursors such as pyruvate and acetyl-coenzyme A, the reductive pentose phosphate cycle of photosynthesis, and the oxidative pentose phosphate cycle. This conversion cannot be accomplished solely by glycolytic enzymes because of the irreversible nature of phosphofructokinase. Racker and Schroeder (1958) have suggested two possible enzymic pathways for the formation of fructose 6-phosphate from triose phosphate. The most direct route is via a phosphate specific for the phosphates attached to carbon-1 of FDP. A combination of aldolase, transaldolase and sedoheptulose diphosphates may provide an alternative pathway.
Date: December 7, 1962
Creator: Saillie, Robert M.
Partner: UNT Libraries Government Documents Department
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A Comparison of OH- Motions in Brucite and Micas

Description: Despite similar atomic arrangement, Brucite (Mg(OH)2) and phlogopite (KMg3(OH)2(Al,Si3)O10) present striking difference in their infrared spectra. A single absorption band is observed in phlogopite whence brucite possesses a total of 15 bands on both sides of the fundamental. A comparison of the hydroxides with micas provides supporting evidence that the complexity of the hydroxide spectra is due to interactions between neighboring hydroxyl groups. Each mineral contains a layer of magnesium ions possessing trigonal symmetry. Both minerals contain hydroxyl ion is located in such a way that it is in contract with three magnesium ions.
Date: December 7, 1962
Creator: Boutin, Henri & Bassett, William
Partner: UNT Libraries Government Documents Department
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Electron Spin Resonance Studies of Gamma-Irradiated Ferrocene

Description: The object of this study was to determine the nature of the free radicals induced in ferrocene by Co60 gamma rays. The irradiations were carried out on the powder at 77°K and on the single crystals at 193°K. The variation of the splitting factor, g, of the signals observed when the single crystals were oriented at different angles relative to the external magnetic field direction, indicated the existence of three types of resonance peaks. It was possible to correlate these variations with the molecular orientations in the crystal unit cell and with the spatial arrangement of the molecular orbitals. Taking into account the spectral changes observed after thermal annealing of the crystal, the existence of the following free radicals has been suggested: 1) a straight molecule-ferricinium ion, 2) a bent molecule-ferricinium ion, and 3) a cyclopentadienyl radical with four protons, the fifth having been transferred to the iron atom. A signal with a cylindrically symmetric g tensor, observed at 77°K, has been assigned to another radical but its nature was not fully established.
Date: December 7, 1962
Creator: Saito, Eiichi
Partner: UNT Libraries Government Documents Department
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Radiobiological Studies of the Columbia River Through December, 1955

Description: Radiobiological studies were made to determine effects of radioactive effluents from the Hanford reactors upon the aquatic biota of the Columbia River and to evaluate related hazards. Data from studies completed between September, 1945, and December, 1955 are presented and interpreted. All forms of life were many times more radioactive than the water they inhabited. Some radioisotopes were much more readily accumulated than others in living organisms. Differences in the concentration of certain radioisotopes by various species of organisms and kinds of body tissue are described; and geographical, seasonal and annual fluctuations in the concentration of radioisotopes in organisms are discussed.
Date: November 7, 1956
Creator: Davis, J. J.; Watson, D. G. & Palmiter, C.C.
Partner: UNT Libraries Government Documents Department
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The Thermal Conductivity of Some Project Materials

Description: Abstract. An apparatus for measuring the thermal conductivities materials which are moderately good conductors of heat is described. Results obtained with a sample of pure Th are given on p. 10, 12, and 13.
Date: December 7, 1944
Creator: Raeth, Charles H.
Partner: UNT Libraries Government Documents Department
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The Thermal Decomposition of Uranium Mononitride

Description: The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.
Date: January 7, 1964
Creator: Vozzella, P. A.; Miller, A. D. & DeCrescente, M. A. (Michael A.)
Partner: UNT Libraries Government Documents Department
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Analysis of Uranium-Nicked Alloys

Description: Abstract. Methods for determination of both uranium and nickel in solutions of these metals are described. Alloys can be dissolved in nitric acid treated with citric acid to complex the uranium, and the nickel precipitated as nicked dimethylglyoxime. The uranium is reduced and titrated with standard ceric sulfate. These methods are for the determination of macro amounts of uranium and nickel with errors on the order of 0.1%.
Date: June 7, 1945
Creator: Ericson, R. P.
Partner: UNT Libraries Government Documents Department
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Third Form of Bismuth Phosphate - X-ray Study

Description: Abstract. In addition to the hexagonal and monoclinic bismuth phosphate precipitates, whose structures are now known, a third crystalline phase has been found to appear in BiPO4 precipitates after (a) extremely long digestion in concentrated nitric acid; (b) oven drying at 800 degrees to 1000 degrees. Thought very small single crystals of the component have been isolated, nor crushed sample contained less than 30% of the beta-form. The cell size and symmetry of the crystal indicates that there ae two bismuth atoms in the cell, and there is no evidence that the compound is not BiPO4. It is suggested that this maty be a third form of BiPO4, stable over a short range of conditions, and tending to revert to the beta-form.
Date: September 7, 1944
Creator: Mooney, Rose Camille Le Dieu
Partner: UNT Libraries Government Documents Department
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Chemical Development, Quarterly Progress Report, July-September, 1953.

Description: Introduction: "During the last quarter, members of the Chemical Development Group have been concerned with six major projects. (1) thermal and radiation properties of organic materials as moderators and coolants, (2) thermal and radiation stability of mirconium hydride, (e) reactor accessibility (transport of radioactive materials in cooling systems, ................. There have been, in addition, a number of smaller service projects, mostly of an analytical nature.:
Date: December 7, 1953
Creator: Loftness, R. L.
Partner: UNT Libraries Government Documents Department
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[TXSSAR Officer Reports: November 7 - 9, 2014]

Description: Officer Reports for the Texas Society, Sons of the American Revolution, compiled November 7 - 9, 2014.
Date: 2014-11-07/2014-11-09
Creator: Texas Society Sons of the American Revolution
Partner: UNT Libraries Special Collections
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[TXSSAR Committee Reports: November 7 - 9, 2014]

Description: Committee Reports for the Texas Society, Sons of the American Revolution, compiled for the November 7 - 9, 2014 Board of Managers meeting.
Date: 2014-11-07/2014-11-09
Creator: Texas Society Sons of the American Revolution
Partner: UNT Libraries Special Collections
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[Texas Education Agency Table II, Fall 1981-82]

Description: A roster determining Texas state school salaries by grade and staff level between 1981 and 1982. Second page includes total enrollment numbers by grade from Crystal City ISD. Third page is a filled facsimile transmittal form.
Date: May 7, 1992
Creator: Texas Education Agency
Partner: UNT Libraries Special Collections
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Nuclear Explosives as Applied to Mining and Mineral Industries

Description: Presentation at the National Western Mining Conference of the Colorado Mining Association, Denver, Colorado, February 7, 1959. Thank you for your invitation to discuss here today some of the aspects of nuclear explosions in mining and mineral industries. I should like this afternoon to dwell briefly upon: (1) The phenology of a nuclear explosion underground. What happens; with what energies are we concerned, and what may be the scientific and industrial results of such an explosion? (2) The safety or radiological hazards involved. If mining men hope someday to use this new and potentially useful source of packaged power, what are some of the problems we may face? First let me emphasize that the nine underground test explosions thus far have resulted in a wealth of data and interesting information which prove that radioactivity and radioactive fall-out can be completely controlled, that seismic effects are relatively minor, that appreciable amounts of heat and shock are generated, that this power might be utilized to serve a useful purpose and that the debris in an explosion area can be worked soon after the detonation.
Date: February 7, 1959
Creator: Rabb, David D.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Maryland

Description: Report documenting the suitability of Maryland for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: May 7, 1951
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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Exploratory User Research for Computational Resource for South Asian Languages

Description: Report for the project, Exploratory User Research for CoRSAL, which was an exploratory ethnographic study to generate a foundational understanding of how different user groups might use a planned language archive for South Asian languages. Their research project was to be used by the CoRSAL team to help plan the design of CoRSAL’s infrastructure, and laid the groundwork for further studies that will take a deeper look at issues surrounding the design and use of the planned language archive.
Date: December 7, 2016
Creator: Al Smadi, Duha; Barnes, Sebastian; Blair, Molly; Chong, Miyoung; Cole-Jett, Robin; Davis, Aaron et al.
Partner: UNT College of Arts and Sciences
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