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Cordilleran Metamorphic Core Complexes and Their Uranium Favorability: Final Report
From objective and scope: The objective of this report us to provide a descriptive body of knowledge on Cordilleran metamorphic core complexes including their lithologic and structural characteristics, distribution within the Cordillera, and their evolutionary history and tectonic setting. We also examine the occurrence of uranium in the context of possibility for uranium concentration.
Date:
November 1980
Creator:
Coney, Peter J. & Reynolds, Stephen J.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Superheat Meeting: September 1959
From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date:
November 3, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Nuclear Superheat Meeting: October 1960
From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.
Date:
November 10, 1960
Creator:
Mravca, Andrew E.
Object Type:
Report
System:
The UNT Digital Library
SRE Fuel Element Damage: An Interim Report
Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date:
November 30, 1959
Creator:
Jarrett, A. A.
Object Type:
Report
System:
The UNT Digital Library
Safe Handling of Chlorine Trifluoride and the Chemistry of the Chlorine Oxides and Oxyfluorides
Abstract: A discussion of the potential hazards of chlorine trifluoride is presented and a series of safe handling procedures is recommended.
Date:
November 11, 1960
Creator:
Farrar, R. Lynn, Jr.
Object Type:
Report
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
November 30, 1963
Creator:
Auleta, J. J.
Object Type:
Report
System:
The UNT Digital Library
Environmental Monitoring Semiannual Report: January-June 1962
From summary: This report summarizes environmental monitoring results for the first six months of 1962.
Date:
November 1962
Creator:
Moore, J. D.; Fisher, W. L. & Rowe, P. A.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Neutron Bombardment on the Electrical Resistance of Aluminum, Beryllium and Tuballoy (Uranium)
Abstract. Wigner effects on aluminum, beryllium, and tuballoy have been studied by the electrical resistance method. Samples were exposed during an interval which would have produced an increase of approximately 22% in resistance of AGOT-K graphite. The resistance of tuballoy increased approximately 1%. It is shown that the increase can be accounted for by the amount of fission product impurity formed during the exposure. Neither aluminum nor beryllium showed any change. In the case of Be, the Wigner effect may be obscured, to some extent, by the approximately .2 - .3 atom % of impurity present in the samples. Based on the increase occurring in ADOT-K graphite, a change of approximately .2 - .5 x10-6 ohm-om might be expected in the case of Be. The accuracy of the method was sufficiently great to detect a change of this magnitude. Other experiments with Be will be undertaken when purer samples are available. Meanwhile, some samples of the present type ae being subjected to further irradiation.
Date:
November 2, 1944
Creator:
Royal, J.
Object Type:
Report
System:
The UNT Digital Library
Extraction of Uranyl Nitrate and Thorium Nitrate by Organic Solvents
Abstract. The separation of uranyl nitrate from aqueous solutions of 0.635 M thorium nitrate, 3 M nitric acid and 3 M calcium nitrate by extraction with organic solvents has been investigated. Solvents which gave good separations were 2-tthyl hexyl acetate, ethyl benzoate, n-butyl either and beta-beta- dichloroethyl ether. In general, higher esters, ethers and alcohols are better for separating uranium from thorium that the lower homologues. Several solvents were tested at lower nitric acid concentrations. Dibutyl cellosolve gave a very good separation when the solution was 0.1 M nitric acid. Of the solvent mixtures studied that of equal parts of n-butyl ether and dibutyl cellosolve gave a good separation.
Date:
November 5, 1945
Creator:
Johnson, O. & Newton, A. S.
Object Type:
Report
System:
The UNT Digital Library
Thermal Conductivity of Metal Interfaces
The coefficients of thermal conductivity of aluminum-bismuth metal-to-metal bonds, and of aluminum and bismuth surfaces in contact under pressure, were measured.
Date:
November 30, 1950
Creator:
Heckman, R. A.
Object Type:
Report
System:
The UNT Digital Library
Mean Square Voltage Fluctuation Measurements With Neutron Sensitive Ion Chambers
To improve gamma discrimination and eliminate d-c cable leakage interference currents, mean square voltage fluctuation measurements have been made on neutron sensitive ion chambers.
Date:
November 1963
Creator:
DuBridge, R. A.
Object Type:
Report
System:
The UNT Digital Library
Development of Fueled Graphite Containing Pyrolytic-Carbon Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems
Abstract: Progress is reported in several areas of development of fueled graphite containing coated particles for nonurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coating under well-controlled conditions. Damage to coated particles during fabrication into a graphite matrix depends on the molding pressure and the volumetric content of coated particles. Vendor-supplied coated particles and fueled graphite spheres have been evaluated extensively in both in- and out-of-reactor tests. Duplex- and triplex-coasted particles have excellent fission-gas retention at 2050 degree F to burnups of 15 at. % burnup. Fueled graphite spheres containing coated particles have good irradiation performance, but the fission-gas release rates are somewhat higher than for unsupported coated particles. Fueled graphite spheres react with water vapor about as rapidly as do Speer Mod-2 and ATJ grades of graphite. The diffusion rates in pyrolytic carbon are the same for uranium, thorium, and protactinium. The diffusion rates in the direction parallel to the deposition plane are much higher than those in the perpendicular direction.
Date:
November 1963
Creator:
Carlsen, F. L., Jr.; Bomar, E. S. & Harms, W. O.
Object Type:
Report
System:
The UNT Digital Library
The Rapid Determination of Nitric Acid and Thorium in Thorium Nitrate Solutions
Abstract. The physico-chemical methods of determining nitric acid and thorium nitrate in solutions containing these two materials were investigated. Conductimetric titration with sodium hydroxide can be used to determine nitric acid accurately. the titration of thorium nitrate requires a separate standardization of the base however, since a basic salt is precipitated rather the normal hydroxide. The titration of thorium is reproductible however, so and empirical standardization can be used. The measurement of the specific gravity and refractivity of the solutions provides a method of determining the concentrations in terms of these two variable. Equations for the concentrations in terms of specific gravity and refractively are given, both in pure solutions and in those saturated with methyl isobutyl ketone.
Date:
November 27, 1945
Creator:
Newton, A. S.; Powell, J. (James), 1932- & Figard, P
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report August 1947 to November 1947, Biology Division
The following document is a compilation of quarterly reports from August 1946 to November of 1947 from the Biology Division of the University of Chicago.
Date:
November 1, 1947
Creator:
Brues, Austin M.
Object Type:
Report
System:
The UNT Digital Library
Visual Efficiency of a Phosphor Bombarded by Plutonium Alpha Particles
This report follows and experiment that was performed to determine the visual efficiency of a phosphor when bombarded by alpha particles.
Date:
November 15, 1948
Creator:
Wakefield, Ernest
Object Type:
Report
System:
The UNT Digital Library
A Method for the Determination of Traces of Metals: [Part] 4. Polarographic Studies.
Report describing an updated method to determine traces of metals under polarographic studies, which operates at a higher cathode current density with a small area of the anode immersed in the solution where an appreciable quantity of iron was present in the solutions that were to be polarographed. The results of these studies are also presented.
Date:
November 1947
Creator:
Bricker, Clark E.; Furman, N. Howell & McDuffie, Bruce
Object Type:
Report
System:
The UNT Digital Library
Division of Reactor Development, Research and Development Programs Quarterly Progress Report: April - June 1964
The programs sponsored by the Division of Reactor Development at Hanford include studies on basic properties of fuel materials and fabrication methods, physics, chemical processing of reactor fuels and radioactive waste, material development, irradiation effects on materials, fuel cycle analysis and advanced concepts, instrumentation, and nondestructive testing techniques. The results of these programs are broadly applicable to the Civilian Application Program.
Date:
November 1964
Creator:
Pacific Northwest Laboratory
Object Type:
Report
System:
The UNT Digital Library
Studies of Porphyrin Metabolism, 3. The Relation of Erythropoiesis to the Excretion of Coproporphyrin by Dogs and Rabbits, and to the Concentration of Coproporphyrin and Protoporphyrin in Rabbit Erythrocytes
Report discussing studies regarding porphyrin excretion and hemoglobin metabolism in animals with phenylhydrazine anemia, and studies regarding the coproporphyrin and protoporphyrin in the red blood cells of rabbits.
Date:
November 25, 1945
Creator:
Schwartz, Samuel; Glickman, Marcia; Hunter, Rosie & Wallace, Jean
Object Type:
Report
System:
The UNT Digital Library
Identification and Characterization of Shielded Isotopes in Uranium Fission
Abstract: "The first shielded isotope, 34th Br-82 has been isolated in fission. Its fission yield is about 3 x 10-(-5)%. This is a direct measurement of the yield of a primary fission product and gives direct information as to the distribution of nuclear charge among primary fission fragments of given mass numbers as discussed by Glendenin and Coryell."
Date:
November 27, 1946
Creator:
Feldman, Milton H.
Object Type:
Report
System:
The UNT Digital Library
Enrico Fermi Fast Breeder Reactor Plant
This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as critical experiments.
Date:
November 1, 1956
Creator:
U.S. Atomic Energy Commission
Object Type:
Report
System:
The UNT Digital Library
A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."
Date:
November 1, 1963
Creator:
Oak Ridge National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel
Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date:
November 15, 1957
Creator:
Ashley, R. L.
Object Type:
Report
System:
The UNT Digital Library
Topical Report on Literature Survey of Treatments for Monazite Sands
The following report covers the literature available in the Battelle library as well as the Atomic Energy Commission (New York, N.Y.) on the processing of monazite sands for thorium and rare earth contents.
Date:
November 1, 1947
Creator:
Willigman, M. & Slowter, E. E.
Object Type:
Report
System:
The UNT Digital Library
Progress Report for the Month of November, 1947 : Contract No. AT 30-1-Gen-202
This report for November, 1947 describes progress regarding chemical work on shales and organic precipitants for uranium.
Date:
November 28, 1947
Creator:
Bearse, A. E.; Croxton, F. C. & Sullivan, John D.
Object Type:
Report
System:
The UNT Digital Library