Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow (open access)

Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow

A relationship is derived the mean square fluctuating current of a hot wire anemometer and the sic turbulent Reynolds stresses in the stream-coordinate system without employing the usual low turbulent intensity approximation. The relatively simple result is a consequence of assuming proportionality between the wire current reading and the perpendicular velocity component instead of the non-linear dependence required by King's law. The assumption is valid for instruments equipped with the proper linearizing circuitry. The stream-coordinate Reynolds' stresses are then related to the cylindrical polar Reynolds stresses.
Date: February 21, 1961
Creator: Wichner, R. P. & Peebles, F. N.
System: The UNT Digital Library
Development of a Cubic Oxide Protective Film on Zirconium (open access)

Development of a Cubic Oxide Protective Film on Zirconium

Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient atomic rearrangement that pieces of ZrO2 normally crack and crumble. It is suggested that the effects of neutrons on monoclinic ZrO2 may be similar so that a protective oxide film on the metal would be destroyed soon after its formation. It might be possible, therefore, that the protective oxide film on zirconium metal which is normally monoclinic might be less resistant to corrosion under radiation damage than a similar film which was cubic.
Date: February 21, 1956
Creator: Johnson, J. R.
System: The UNT Digital Library
HFIR Beryllium Reflector Preliminary Design Report (open access)

HFIR Beryllium Reflector Preliminary Design Report

This report considers the HFIR reflector design criteria and presents a summary of the reflector design. The reflector type chosen as complying best with the established criteria consists of a 3 in. thick removable beryllium annulus utilizing four concentric cylinders with cooling water flowing through the annuli between cylinders, and an outer 9 in. thick permanent beryllium annulus with axial circular coolant holes. Reflector support structures and experimental facilities are described and probable beryllium replacement costs are indicated.
Date: February 21, 1961
Creator: Hilvety, Neil
System: The UNT Digital Library
Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work (open access)

Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work

This report is presented in order to provide a satisfactory system of symbols and identifications for process-instrumentation equipment and to promote a uniformity of practice that will simplify and expedite instrumentation work. It is intended that the systems presented here should be capable of designating and identifying the multitude of instrumentation items which are used for control and operation of conventional processes, as well as for specialized work peculiar to ORNL. Instrument Society of America standards have been adhered to whenever practical.
Date: February 21, 1958
Creator: Adams, R. K.; Davis, D. G. & Hyland, R. G.
System: The UNT Digital Library
Interim Report - Status of Small Pipe and Tube Disconnects for MSRE Auxiliary Lines (open access)

Interim Report - Status of Small Pipe and Tube Disconnects for MSRE Auxiliary Lines

To date, three types of metal-to-metal seal disconnects have been subjected to thermal cycling and make-break tests. In addition, a commercial disconnect has been procured for testing.
Date: February 21, 1961
Creator: Holz, P. P.
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: October 1957 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: October 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.
Date: February 21, 1958
Creator: MacPherson, H. G.
System: The UNT Digital Library
The Technology of Uranium Dioxide a Reactor Material (open access)

The Technology of Uranium Dioxide a Reactor Material

Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material. For other applications the oxide may be fabricated in bulk form such as pellets, rods, plates, or blocks.There is a need for knowledge of the properties of the properties of this oxide, particularly as it affects fabrication in the various forms required. This knowledge is also required by reactor designers and engineers. There is in addition a challenging field for basic studies of sintering rates, oxidation behavior and other phenomena. Fabrication techniques have been developed to produce uranium oxide in various forms with consideration given to the economy of production. The continued application of basic knowledge of these materials has led to simpler. more practical means of fabrication and has thus widened the scope of their use in atomic reactors.
Date: February 21, 1956
Creator: Johnson, J. R.; Doney, L. M.; Fulkerson, S. D.; Taylor, A. J.; Warde, J. M. & White, G. D.
System: The UNT Digital Library