Resource Type

Analytical Chemistry Division Annual Progress Report, December 31, 1960 (open access)

Analytical Chemistry Division Annual Progress Report, December 31, 1960

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date: 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Analytical Chemistry Division Annual Progress Report, May 20, 1970 (open access)

Analytical Chemistry Division Annual Progress Report, May 20, 1970

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date: September 1970
Creator: Oak Ridge National Laboratory
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.
System: The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor (open access)

Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date: December 23, 1960
Creator: Wick, E. A. & Heestand, R. L.
System: The UNT Digital Library
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.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1968 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1968

Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date: September 1968
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Chromosomal Aberrations in a Natural Population of Chironomus Tentans Exposed to Chronic Low-Level Environmental Radiation (open access)

Chromosomal Aberrations in a Natural Population of Chironomus Tentans Exposed to Chronic Low-Level Environmental Radiation

From introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."
Date: January 29, 1964
Creator: Blaylock, B. Gordon; Auerbach, S. I. & Nelson, D. J.
System: The UNT Digital Library
Civil Defense Research Project Annual Progress Report: March 1966 - March 1967 (open access)

Civil Defense Research Project Annual Progress Report: March 1966 - March 1967

Report containing the results of Oak Ridge National Laboratory's research relating to civil defense.
Date: December 1967
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution (open access)

Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
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.
System: The UNT Digital Library
A Compilation of Information on Gamma-Ray Spectra Resulting from Thermal-Neutron Capture (open access)

A Compilation of Information on Gamma-Ray Spectra Resulting from Thermal-Neutron Capture

Report containing a series of thermal-neutron capture gamma-ray spectra collected in a tabular form.
Date: 1961
Creator: Troubetzkoy, E. & Goldstein, H.
System: The UNT Digital Library
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables (open access)

A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
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.
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.
System: The UNT Digital Library
Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4 (open access)

Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4

Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.
Date: May 1, 1962
Creator: Jenks, G. H.
System: The UNT Digital Library
Electronuclear Research Division Annual Progress Report, December 31, 1963 (open access)

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
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.
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.
System: The UNT Digital Library
Environmental Analysis of NS "Savannah" Operation at Camden (open access)

Environmental Analysis of NS "Savannah" Operation at Camden

Report regarding the nuclear ship "Savannah" and the consequences of nuclear activity that it would release into the surrounding area at its proposed startup site, Camden, New Jersey. Scenarios include activity being released into the atmosphere and hydrosphere, damage to equipment, and effects on a population.
Date: 1960
Creator: Cottrell, William B.; Mann, L. A.; Parker, F. L. & Schmidt, G. D.
System: The UNT Digital Library
Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination (open access)

Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination

Economic and hazards calculation of pot calcination of Purex and Thorex wastes.
Date: October 16, 1961
Creator: Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.
System: The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums (open access)

Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Bourgette, D. T.
System: The UNT Digital Library
Experimental Stress Analysis of EGCR Pressure Vessel (open access)

Experimental Stress Analysis of EGCR Pressure Vessel

Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.
Date: 1961
Creator: Greenstreet, B. L.; Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R. & LaVerne, M. E.
System: The UNT Digital Library
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor (open access)

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
System: The UNT Digital Library