Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology 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
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
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961 (open access)

Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date: November 1968
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Nuclear Safety Program Annual Progress Report for Period Ending December 31, 1967 (open access)

Nuclear Safety Program Annual Progress Report for Period Ending December 31, 1967

Annual progress report of safety program for several laboratory divisions.
Date: April 1968
Creator: unknown
Object Type: Report
System: The UNT Digital Library
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 (open access)

U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1

First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
Date: August 1965
Creator: Cottrell, William B. & Savolainen, A. W.
Object Type: Report
System: The UNT Digital Library
A Comparison of Gas-Turbine and Steam-Turbine Power Plants for Use with All-Ceramic Gas-Cooled Reactors (open access)

A Comparison of Gas-Turbine and Steam-Turbine Power Plants for Use with All-Ceramic Gas-Cooled Reactors

Report that "compares gas turbines with steam turbines as means of producing electric power from gas-cooled reactors with all-ceramic fuel elements." (p. 1)
Date: July 1965
Creator: Fraas, A. P. & Ozisik, M. N.
Object Type: Report
System: The UNT Digital Library
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes (open access)

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.
Object Type: Report
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1965 (open access)

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.
Object Type: Report
System: The UNT Digital Library
Irradiation Effects in the EGCR Fuel (open access)

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.
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
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965 (open access)

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.
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
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops (open access)

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.
Object Type: Report
System: The UNT Digital Library
Review of Radioisotopes Program, 1964 (open access)

Review of Radioisotopes Program, 1964

Report issued by the Oak Ridge National Laboratory discussing a review of the Radioisotopes Program during 1964. Research and experimental projects conducted during 1964 is presented. This report includes tables, illustrations, and photographs.
Date: May 1965
Creator: Gillette, J. H.
Object Type: Report
System: The UNT Digital Library
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine (open access)

An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine

Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
Date: April 1965
Creator: Garrett, M. W.
Object Type: Report
System: The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV (open access)

Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV

Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date: April 1965
Creator: deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
Object Type: Report
System: The UNT Digital Library
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes (open access)

Optical Mapping of Oak Ridge Research Reactor Experiment Tubes

Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
Date: April 1965
Creator: Abbatiello, A. A.
Object Type: Report
System: The UNT Digital Library
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi (open access)

Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi

Report concerning the production of gamma ray spectra of gamma rays by the interaction of ~160-MeV protons with beryllium, carbon, oxygen, Aluminum, carbon monoxide, and bismuth. This also includes descriptions of the apparatus used and a discussion of the results.
Date: April 1965
Creator: Zobel, W.; Maienschein, F. C. & Scroggs, R. J.
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
High-Density Concrete for Gamma and Neutron Attenuation (open access)

High-Density Concrete for Gamma and Neutron Attenuation

Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
Object Type: Report
System: The UNT Digital Library
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963 (open access)

Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963

Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: McCurdy, H. C.
Object Type: Report
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.1

This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Object Type: Report
System: The UNT Digital Library
Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2 (open access)

Smoothed Thermocouple Tables of Extended Significance (°C), Volume 2: Section 2.2

This report is a segment providing smoothed thermocouple tables of extended significance in degrees Celsius (°C) for [section name]. It includes [1] a figure illustrating the difference in microvolts between the values in the smoothed table and those in the reference table and [2] a reference table containing (i) a tabulation of smoothed emf (in absolute millivolts) vs. temperature for a specific thermocouple and (ii) a tabulation of emf differences.
Date: March 1965
Creator: Adams, R. K. & Davisson, E. G.
Object Type: Report
System: The UNT Digital Library