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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Partner: UNT Libraries Government Documents Department
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Pressure and Thermal Stresses at a Pipe Attachment to a Sphere

Description: Abstract: Design nomographs and equations have been prepared for determining the bending stresses and hoop stresses at the junction of a cylinder and sphere when: (1) Internal pressure exists in the sphere and (2) There is a difference in average temperature between the cylinder and the sphere. A correlation of calculated stresses and photoelastically determined stresses for models with internal pressure is presented.
Date: September 21, 1959
Creator: Deagle, Lorenzo
Partner: UNT Libraries Government Documents Department
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Practical Methods for the Reduction of Strain Gage Data

Description: The error that results when it is attempted to evaluate stress from a reading taken on a single element SR-4 strain gage in a biaxial stress field is discussed. A method is presented for relating SR-4 rosette strain gage readings directly to the biaxial stress state without the necessity of first converting strain gage readings to true strains. Correction formulas are presented for use when single element SR-4 gages are used as rosette elements or as stress gages.
Date: September 7, 1955
Creator: Dove, Richard C.
Partner: UNT Libraries Government Documents Department
open access

Temperature Distribution and Thermal Stress in Reactor Core APPR-1

Description: The study was conducted to determine the adequacy of the fuel element structural design of APPR-1. The results obtained lead to the conclusion that the element design is structurally sound for all normal operating conditions from the standpoint of thermal stress.
Date: unknown
Creator: Berggren, W. P. & Kroeger, H. R.
Partner: UNT Libraries Government Documents Department
open access

The Preliminary Shield Design for the 50 MW Commercial Reactor

Description: The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date: unknown
Creator: Bagley, R. O., Jr.
Partner: UNT Libraries Government Documents Department
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