A Single Stage Axial Compressor Blade Test Facility (open access)

A Single Stage Axial Compressor Blade Test Facility

Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date: January 13, 1964
Creator: Fee, G. G.
System: The UNT Digital Library
Stratospheric Monitoring Program (open access)

Stratospheric Monitoring Program

"Design work was completed and construction initiated on a prototype field altimeter based on the gas density dependence of Townsend discharge current in an electrical discharge. The design of an ion tracer air velocity meter for laboratory applications, and construction of three units were successfully completed. Theoretical and experimental support is presented, showing the applicability of the ion tracer system to the accurate measurement of linear gas velocity. The operating range of the laboratory meter is 150 to 2500 ft/min at ambient pressures between 200 mu and 30.0 mm Hg. Further investigations on the application of the ion tracer concept to flowrate measurements are presented. By generating velocity profile curves with an ion tracer calibrated thermoanemometer, it was possible to determine the flowrate for 2 flow and pressure conditions; 37.5 cfm at 19.6 mm and 75 cfm at 9.8 mm Hg. Comparison with a calibrated Rotameter technique was within 5% in both cases. Also presented are some preliminary investigations leading to the development of a generalized ion tracer flowmeter for low gas densities. Results of some supplemental electrical discharge experiments in rarefied atmospheres are described. It was observed that electrical oscillations could be produced in a low density gas discharge, …
Date: January 13, 1963
Creator: Cravitt, S.; Lilienfeld, P. & Foldes, A.
System: The UNT Digital Library
SM-1 Reactor Core Inspection at 2/3 Core Life : March 7, 1959 to May 17, 1959 (open access)

SM-1 Reactor Core Inspection at 2/3 Core Life : March 7, 1959 to May 17, 1959

Abstract: This technical report is concerned with the program and results of the SM-1 reactor vessel head removal and core inspection at Fort Belvoir, Virginia from the period March 7, 1969 to May 17, 1959. It covers the operating procedures in detail and records the conditions found and problems encountered in order to make a record for reference in future work of this nature. The major objective of the program, to obtain irradiation data on the SM-1 type core, has been met. The boron control rod elements were found unsatisfactory for full core life, and europium oxide elements were placed in the core for future irradiation stability data. A major problem was experienced with the cracked pressure vessel head studs. The methods developed for the removal of the broken studs are presented. The complete metallurgical study of the stud failure from stress corrosion is included as Appendix B.
Date: January 13, 1960
Creator: Obrist, C. H.; Byrne, B. J.; Connolly, T. F.; Foley, D. D.; Lichtenberger, R. V.; Mackay, S. D. et al.
System: The UNT Digital Library
Thermonuclear Project Semiannual Progress Report: for Period Ending July 31, 1960 (open access)

Thermonuclear Project Semiannual Progress Report: for Period Ending July 31, 1960

From Introduction: "The present semiannual progress report introduces more active consideration than has been given in the past (by us, at least) to the importance of energy degradation in DCX-like devices. The following pages introduce also a new major apparatus designated as DCX-2. Some of these concepts cannot as yet be released publicly and therefore Chap. 3 of this report, covering the DCX-EP-B design, is being issued separately, with restricted distribution, as ORNL-3044."
Date: January 13, 1961
Creator: unknown
System: The UNT Digital Library
Specification for Cleaning Metal Components and Systems for Liquid-Metal Cooled Power Reactors (open access)

Specification for Cleaning Metal Components and Systems for Liquid-Metal Cooled Power Reactors

"The degree of cleanliness is defined, and the methods and materials to be used are outlined for carbon and low alloy steels, 300 and 400 series ferritic and austenitic stainless steels, special Ni-Cr base heat-resistant hard-facing and high-temperature brazing alloys, and some non-ferrous materials."
Date: January 13, 1958
Creator: Kovac, L.
System: The UNT Digital Library