The High Flux Isotope Reactor: Volume 1, A Functional Description (open access)

The High Flux Isotope Reactor: Volume 1, A Functional Description

Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.
Date: May 1964
Creator: Binford, F. T. & Cramer, E. N.
System: The UNT Digital Library
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings (open access)

The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings

Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date: August 1964
Creator: Binford, F. T.; Cramer, E. N. & Cramer, E. N.
System: The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report, September 1, 1963 (open access)

Instrumentation and Controls Division Annual Progress Report, September 1, 1963

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: June 1964
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor (open access)

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
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.
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress is presented. This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Briggs, R. B.
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964 (open access)

Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: July 1964
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963 (open access)

Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
Date: 1964-12~
Creator: Oak Ridge National Laboratory. Analytical Chemistry Division.
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.
System: The UNT Digital Library
Photochemistry of Nucleic Acids, and its Biological Implications (open access)

Photochemistry of Nucleic Acids, and its Biological Implications

The series of papers that we are about to discuss is primarily concerned, not as the first part of the session title indicates, with photochemistry of nucleic acids, but, as the second part indicates, with the biological implications of the photochemistry. We know that ultraviolet acts on nucleic acids in cells, and we know a good deal about the photochemistry of this interaction in vitro. The question we ask here is, which test tube reactions are of importance to the survival of the cell?
Date: July 1964
Creator: Jagger, John, 1924-
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.
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.
System: The UNT Digital Library
Recent Developments in DC Polarography (open access)

Recent Developments in DC Polarography

This paper summarized the work at ORNL in controlled-potential dc polarography since mid 1959 and states conclusion and viewpoints that have been reached in the course of this work. The following topics are discussed: (1) Potentiostatic Compensation for Polarographic Cell Resistance; (2) Time-Derivative DC Polarography; (3) Signal-to-Noise Ratio (S.N); (4) Resolution; and (5) DC Polarography in Non Aqueous Solvents and, Particularly, in Solvent Extracts.
Date: July 1964
Creator: Fisher, D. J.; Belew, W. L. & Kelley, M. T.
System: The UNT Digital Library
Recent Studies of Boiling Burnout (open access)

Recent Studies of Boiling Burnout

Five recent investigations of the critical heat flux in water systems are described. These studies were conducted in the interval from early 1963 through the present. The five studies are (1) Pool studies: inherent uncertainty in the critical heat flux; (2) Pool studies: heat transfer inside of horizontal, open ended heated tubes immersed in a pool; (3) Pool studies: natural-convection burnout of closed vertical channels; (4) Forced-convection investigations; subcooled boiling and burnout with heated twisted tapes; and (5) Forced-convection investigations; swirl-flow forced-convection bulk-boiling loop.
Date: April 1964
Creator: Gambill, W. R.
System: The UNT Digital Library
A Simple Quasi Reference Electrode … Applications in Controlled-Potential Polarography and Voltammetry and in Chronopotentiometry (open access)

A Simple Quasi Reference Electrode … Applications in Controlled-Potential Polarography and Voltammetry and in Chronopotentiometry

The quasi reference electrode ( Q.R.E. ) is a bright platinum wire or other inert conductor immersed directly in the solution; it may have a very small area. It is used instead of a true reference electrode but must be used with potentiostatic or other circuits that prevent the drawing of cell current through the Q.R. E. When used in appropriate situations, the results obtained by use of a Q.R.E. are like those obtained with a true reference electrode except for the lack of thermodynamic meaning of the Q.R.E. potential ; hence , this simple electrode is called a quasi reference electrode.
Date: July 1964
Creator: Fisher, D. J.; Belew, W. L. & Kelley, M. T.
System: The UNT Digital Library
Solid State Division Annual Progress Report, May 31, 1964 (open access)

Solid State Division Annual Progress Report, May 31, 1964

Report containing ongoing research and development of the Solid State Division of the Oak Ridge National Laboratory.
Date: October 1964
Creator: Oak Ridge National Laboratory. Solid State Division.
System: The UNT Digital Library
Some Applications of the Distorted Wave Approximation for Direct Nuclear Reactions (open access)

Some Applications of the Distorted Wave Approximation for Direct Nuclear Reactions

The subject which I will discuss is the distorted - waves theory of direct reactions and its application to the study of nuclei. I shall mainly be concerned with a study of the reaction theory, its range of validity, and its ability to give quantitative information about nuclear structure.
Date: July 1964
Creator: Bassel , R. H.
System: The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory (open access)

Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory

Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date: April 1964
Creator: Trauger, Donald B.
System: The UNT Digital Library
Southwest Experimental Fast Oxide Reactor Development Program: First Quarterly Report, April-June 1964 (open access)

Southwest Experimental Fast Oxide Reactor Development Program: First Quarterly Report, April-June 1964

From abstract: "This report summarizes the work performed on the Research and Development Program for the Southwest Experimental Fast Oxide Reactor."
Date: July 1964
Creator: Horst, K. M.
System: The UNT Digital Library
A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C (open access)

A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C

The experimental details, mathematical models, and typical data for a rapid comparative method for thermal conductivity measurements are presented. The method consists of measuring the temperature change of a small silver sphere after it is brought in contact with a small disk-shaped specimen which was initially at ta higher temperature. This temperature change was calibrated in the range of 50 to 400 degrees C by making measurements on samples of know thermal conductivity. The accuracy of this technique was shown to be between than +-10% with a reproducibility of at least +-2.5%. Using known transport mechanisms for heat conduction in solids and the temperature dependency of the electrical conductivity, a means to judiciously extrapolate thermal conductivity data obtained between 50 and 400 degree C to high temperature is presented.
Date: August 11, 1964
Creator: Kollie, T. G.; McElroy, D. L.; Graves, R. S. & Fulkerson, W.
System: The UNT Digital Library
Thermal Properties of Grade CGB Graphite (open access)

Thermal Properties of Grade CGB Graphite

Grade CGB graphite is a nuclear graphite which is basically an extruded petroleum coke bonded with coal tar pitch. No carbon blacks are used and the low-permeation graphite is finished through a series of impregnations and heat treatments with a final heat treatment of all components to 2800 degrees C. A listing of the results obtained is given in Table 1. The results at 51 degrees C are considered questionable. There was a slight contamination of the 90% Pt 10% Rh-Pt thermocouples at 910 degrees C but it was not sufficient to doubt the validity of the 910 degrees C results. However, the results obtained at 1015 degrees C should be disregarded because of severe thermocouple instabilities. In addition, the electrical resistance of the core heater at 603 degrees C indicated the thermocouples had a -10 to -15 degree error which is sufficient justification to disregard the 605 degrees C data.
Date: August 11, 1964
Creator: Moore, J. P. & Godfrey, T. G.
System: The UNT Digital Library
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride (open access)

Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride

Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Date: October 1964
Creator: Gens, T. A.
System: The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment (open access)

Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment

Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date: April 1964
Creator: Sease, J. D.; Lotts, A. L. & Davis, F. C.
System: The UNT Digital Library