3,530 Matching Results

Search Results

Results: 1 - 24 next
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

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
open access

[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
open access

[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
Location: 31.078106 -97.367942
Partner: UNT Libraries Special Collections
open access

[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
open access

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
open access

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
open access

Spectral Lines of Curium from 3100 A to 4200 A

Description: Abstract: Fifty-four spectral lines of curium are listed together with estimated intensities. A brief description of the manner of taking the spectra and of measuring the lines are given.
Date: April 7, 1948
Creator: Conway, John G. & Moore, Milton F.
Partner: UNT Libraries Government Documents Department
open access

Studies of the Metabolism of Certain Fission Products and Plutonium

Description: A short survey of some of the metabolic relationships of the elements, cerium, colurbium, plutonium, strontium, yttrium, and zirconium is presented. While the results of internally deposited radium have not been investigated in these experiments, they have been extensively studies by others. Because so much is known of its biological effects, it has been included in this historical survey.
Date: August 7, 1950
Creator: Kawin, Bergane; Copp, D. H. & Hamilton, J. G.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12

Description: An experiment now in progress should give some accurate information about the thermal neutron absorption cross section of carbon 12. This report outlines and summarizes this experiment and analyzes it to determine the main sources of error and the probably error in the final result.
Date: October 7, 1953
Creator: Seppi, E. J.
Partner: UNT Libraries Government Documents Department
open access

The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

Description: From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
Partner: UNT Libraries Government Documents Department
open access

Solutions of Gallium(I) Salts in Aqueous Base

Description: This technical report outlines the results and characteristics of the reactions of gallium (I) salts in aqueous bases. This report also details experimental results.
Date: June 7, 1962
Creator: Corbett, John D. (John Dudley), 1926-2013
Partner: UNT Libraries Government Documents Department
open access

Experimental Training Model for Closed Chest Cardiac Massage Developed at the Ames Laboratory

Description: From introduction: "This article describes a training aid that was at the Ames Laboratory in order to give the plant protection group of the Laboratory an opportunity to practice closed chest cardiac massage on a simulated model. Details of the model are given so that professional or semi-professional people who may be faced with a sudden emergency requiring immediate action may duplicate this training aid."
Date: June 7, 1962
Creator: Padellford, Ralph
Partner: UNT Libraries Government Documents Department
Back to Top of Screen