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OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations
This report describes a computer program--Oak Ridge Thermal Ellipsoid Plot program (OR TEP)--for drawing crystal structure illustrations with a mechanical plotter.
Date:
June 1965
Creator:
Johnson, Carroll K.
System:
The UNT Digital Library
In-Pile Test of Prototype ML-1 Fuel Elements
Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date:
June 1964
Creator:
Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
System:
The UNT Digital Library
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia
From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."
Date:
June 7, 1962
Creator:
Kitts, F. G. & Clark, W. E.
System:
The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964
Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Physics Division.
System:
The UNT Digital Library
Procedures for Fabricating Aluminum-Base ATR Fuel Elements
Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Date:
June 1964
Creator:
Beaver, R. J.; Patriarca, P. & Adamson, G. M.
System:
The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual
Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Date:
June 1964
Creator:
Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.
System:
The UNT Digital Library
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Date:
June 1965
Creator:
Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.
System:
The UNT Digital Library
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C
In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date:
June 10, 1963
Creator:
Jenks, G. H.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
June 1965
Creator:
Trauger, D. B. & Whitman, G. D.
System:
The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
June 1967
Creator:
Borkowski, C. J.; Dandl, R. A.; Epler, E. P. & Harrill, C. S.
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date:
June 1965
Creator:
Briggs, R. B.
System:
The UNT Digital Library
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
June 27, 1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Welding Plutonium-Containing Fuel Elements
Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).
Date:
June 1964
Creator:
Lemon, L. C.; Ross, W. T. & Bailey, W. J.
System:
The UNT Digital Library
Electronuclear Research Division Annual Progress Report, December 31, 1963
Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Electronuclear Research Division.
System:
The UNT Digital Library
Irradiation Effects in the EGCR Fuel
From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date:
June 1965
Creator:
Baumann, C. D.
System:
The UNT Digital Library
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes
Report documenting the problems, design, and operation of countercurrent liquid-foam columns.
Date:
June 1965
Creator:
Haas, P. A.
System:
The UNT Digital Library
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.
Date:
June 1965
Creator:
Jansen, D. H. & Hoffman, E. E.
System:
The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date:
June 1961
Creator:
Muraoka, J.
System:
The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date:
June 1961
Creator:
Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System:
The UNT Digital Library
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy
This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date:
June 1961
Creator:
Todd, R. H.
System:
The UNT Digital Library
A New Model Concept for Large Nuclear Reactors
Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Date:
June 1964
Creator:
Harvey, R. A.
System:
The UNT Digital Library
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques
Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.
Date:
June 1964
Creator:
Ryan, B. A.
System:
The UNT Digital Library
Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results
Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).
Date:
June 30, 1964
Creator:
Zeutschel, M. F. & Dixon, N. E.
System:
The UNT Digital Library