[3D Viewer]

Black cardboard viewer with plastic lenses, "for printed stereo photographs." It has scored portions and instructions for folding the cardboard to create a standing viewer to look through the lenses and keep the image at a distance.
Date: 1965
Creator: Stereo Magniscope, Inc.
Object Type: Physical Object
System: The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (open access)

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 3, 1961
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Object Type: Report
System: The UNT Digital Library
OR TEP: a FORTRAN Thermal-Ellipsoid Plot Program for Crystal Structure Illustrations (open access)

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.
Object Type: Report
System: The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958 (open access)

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: June 24, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Object Type: Report
System: The UNT Digital Library
The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements (open access)

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

"The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Object Type: Report
System: The UNT Digital Library
Thermocouple Design and Test Program for Reactor Projects (open access)

Thermocouple Design and Test Program for Reactor Projects

Report regarding thousands of hours of testing Chromel P-Alumel thermocouple material with MgO insulation.
Date: 1959
Creator: DeLorenzo, J. T.
Object Type: Report
System: The UNT Digital Library
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia (open access)

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.
Object Type: Report
System: The UNT Digital Library
The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual (open access)

The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual

Report describing a computing device called the Four-Linear-Element Package Analog Computer (FLEPAC) at the Oak Ridge National Laboratory. The report includes a description of FLEPAC as well as instructions for its use.
Date: 1959
Creator: Green, F. P.
Object Type: Report
System: The UNT Digital Library
Generalized Heat Conduction Code for the IBM-704 Computer (open access)

Generalized Heat Conduction Code for the IBM-704 Computer

Report regarding a code that solves "steady-state and/or transient heat conduction problems in three-dimensional geometry" (p. 1).
Date: 1959
Creator: Fowler, T. B. & Volk, E. R.
Object Type: Report
System: The UNT Digital Library
Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units (open access)

Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units

Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.
Date: 1962
Creator: Fraas, A. P.
Object Type: Report
System: The UNT Digital Library
Corn Pone: A Multigroup, Multiregion Reactor Code (open access)

Corn Pone: A Multigroup, Multiregion Reactor Code

Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
Object Type: Report
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964 (open access)

Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964

Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date: January 1965
Creator: Kelley, M. T.; Susano, C. D. & Fisher, D. J.
Object Type: Report
System: The UNT Digital Library
Applied Health Physics Annual Report for 1963 (open access)

Applied Health Physics Annual Report for 1963

Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Object Type: Report
System: The UNT Digital Library
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956 (open access)

Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

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: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
Object Type: Report
System: The UNT Digital Library
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968 (open access)

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date: February 1969
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Object Type: Report
System: The UNT Digital Library
Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968 (open access)

Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968

Report containing material from several Oak Ridge National Laboratory groups regarding nuclear safety.
Date: June 1969
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964 (open access)

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.
Object Type: Report
System: The UNT Digital Library
Mechanical Properties of Some Refractory Metals and their Alloys (open access)

Mechanical Properties of Some Refractory Metals and their Alloys

Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.
Date: April 1964
Creator: McCoy, H. E., Jr.; Stephenson, R. L. & Weir, J. R., Jr.
Object Type: Report
System: The UNT Digital Library
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy (open access)

Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy

Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
Date: March 1965
Creator: Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.
Object Type: Report
System: The UNT Digital Library
Procedures for Fabricating Aluminum-Base ATR Fuel Elements (open access)

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.
Object Type: Report
System: The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual (open access)

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.
Object Type: Report
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 (open access)

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.
Object Type: Report
System: The UNT Digital Library
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor (open access)

Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor

Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.
Date: 1964
Creator: Knight, R. W. & Leitten, C. F., Jr.
Object Type: Report
System: The UNT Digital Library