High Flux Isotope Reactor: a General Description (open access)

High Flux Isotope Reactor: a General Description

Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962 (open access)

Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962 (open access)

Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 15, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961 (open access)

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
System: The UNT Digital Library
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964 (open access)

Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date: July 15, 1964
Creator: Howard, C. L.
System: The UNT Digital Library
Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program (open access)

Power Reactor Fuel Processing Pilot Plant: Brookhaven Fuel Program

Results of processing 47 metric tons of Brookhaven spent reactor fuel are summarized.
Date: December 15, 1960
Creator: McDuffee, W. T.
System: The UNT Digital Library
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C (open access)

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
System: The UNT Digital Library
Oak Ridge National Laboratory Target Preparation Program (open access)

Oak Ridge National Laboratory Target Preparation Program

In early 1961 a Target Fabrication Center was established at Oak Ridge National Laboratory to carry out the routine preparation of a wide variety of targets and to provide research and development support to the target program. Although most of the effort concerned enriched stable isotopes, both normal and radioactive materials are also handled. With the aid of rolling mills, resistance-heat and electron-bombardment vacuum evaporation, presses, and electroplating equipment, targets of elements and compounds are prepared which cover a broad range of thicknesses and sizes, in both supported and self-supporting forms. Thicknesses vary from a few micro-inches to dimensions limited in many cases only by the amount of material available. Although there are certain limitations imposed by the chemical reactivity, the development effort is supporting targets of most elements and compounds.
Date: January 15, 1963
Creator: Kobisk , E. H
System: The UNT Digital Library
Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe (open access)

Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical forms for both the case of constant heat flux at the pipe wall and the case of constant temperature at the pipe wall. The heat transfer coefficients computer in this investigation are compared with existing experimental dat, and a discussion of the parameters affecting the heat transfer characteristics of fluids in turbulent motion in circular pipes is presented.
Date: September 15, 1960
Creator: Hefner, R. J.
System: The UNT Digital Library
Preprocessing of Procedure in the ORACLE-Algol Translator (open access)

Preprocessing of Procedure in the ORACLE-Algol Translator

This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on the use of procedures. The result, however, retains the more basic features of the Algol 60 procedure concept. Most of the algorithms published in the Communications of the Association for Computing Machinery can be handled by the preprocessor with few minor or no changes.
Date: May 15, 1961
Creator: Bumgarner, L. L.
System: The UNT Digital Library