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Cross Section Program at ORNL

Description: Short reports to the members of the Nuclear Cross Section Advisory Group from three groups: (1) High voltage group; (2) Fast chopper time-of flight spectrometer; and (3) Electronuclear research division.
Date: January 21, 1957
Creator: Harvey, J. A. & Fowler, J. L. (Joseph L.)
Partner: UNT Libraries Government Documents Department
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Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work

Description: 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 Socie… more
Date: February 21, 1958
Creator: Adams, R. K.; Davis, D. G. & Hyland, R. G.
Partner: UNT Libraries Government Documents Department
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Interim Report of APPR Irradiation Test Program at MTR

Description: It is the purpose of this memo to clarify and revise burnup calculations for the APPR irradiation program and to present a proposed irradiation schedule. the report will also be in the nature of a review of the program.
Date: January 21, 1957
Creator: Gross, E. E. & Schaffer, L. D.
Partner: UNT Libraries Government Documents Department
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Test of Stainless Steel Freeze Jacket to be Used on 1/2-inch High Pressure and High Temperature Process Lines

Description: In order to test the operation of a freeze jacket in air with the process fluid closely following the conditions found in the high pressure circulation loop of a homogeneous reactor, or, 2000 psi and 300C, a test loop was built and used in conjunction with existing refrigeration equipment. The freeze jacket was made of 5/16-in. type 346 stainless steel tubing wrapped around and welded to a 1/2-in. stainless steel process line. It was concluded that for these reactor operating conditions, only a… more
Date: January 21, 1957
Creator: Draper, B. D.
Partner: UNT Libraries Government Documents Department
open access

Beryllium

Description: The information concerning beryllium assembled herein has been selected primarily to provide information that might be pertinent to the design of the ART. The creep-rupture data in the literature have been obtained from vacuum cast and extruded beryllium, rather than from the hot-pressed beryllium which will be used in the ART. A research program is being conducted by the Brush Beryllium Company, under contract to the Oak Ridge National Laboratory, which will eventually provide the design engi… more
Date: March 21, 1957
Creator: Whitman, M. J.
Partner: UNT Libraries Government Documents Department
open access

Anisotropic Elastic Scattering of Neutrons

Description: In an elastic collision the neutron loses part of its kinetic energy to the nucleus with both the kinetic and momentum of the system being conserved. However, for many elements the scattering is not isotropic in the center-of-mass system at the higher neutron energies. Many of the present reactor multigroup codes include anisotropic scattering at the high neutron energies, while many others assume isotropic scattering at all energies. In order to consider some of the effects of including anisot… more
Date: March 21, 1957
Creator: Copenhaver, C. M.
Partner: UNT Libraries Government Documents Department
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