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Measurement of thermal stresses within an experimental nuclear-reactor vessel head

Technique employed in measuring thermal stresses in interior of head, under simulated operating conditions of steady-state pressure and temperature transients, is described

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Abstract

This paper describes certain tests and techniques employed in measuring stresses within an experimental nuclear-reactor head of unusual design.

The incorporation of certain desired design features necessitated that the head be extremely thick. Due to the thickness and its complex geometry, it was considered desirable to determine stress distribution within the head under conditions of steady-state pressure combined with rapid heating and cooling transients within the reactor, in order to determine safe limits for the operation of the head.

A photoelastic study of a three-dimensional model of the reactor head was completed in 1956; this study permitted prediction of the stress distribution throughout the head as a function of internal pressure, but it was not possible to assimilate the head thermal stresses by photoelastic means. It is the purpose of this paper to describe the technique employed in measuring thermal stresses in the interior of the head, under simulated operating conditions of steady-state pressure and temperature transients.

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References

  1. “Design Values for Thermal Stress in Ductile Materials.” The American Society of Mechanical Engineers. Paper No. 58-Met-1 by B. F. Langer, August 1957. Also published in Welding Journal Research Supplement (September 1958.)

  2. “Tentative Structural Design Basis for Reactor Pressure Vessels and Directly Associated Components,” by B. F. Langer, Westinghouse Electric Corp., Apr. 1, 1958. Available from U. S. Department of Commerce, Office of Technical Services, Washington, D. C., Report No. PB-151987.

  3. “Proceedings of a Panel Discussion on Thermal Stresses,” by B. F. Langer, Westinghouse Electric Corp.; L. F. Coffin, Jr., General Electric Research Laboratory; R. U. Blaser, The Babcock and Wilcox Co.; W. E. Cooper, Knolls Atomic Power Laboratory, Proceedings of the Society for Experimental Stress Analysis, XV, No. 2, p. 119.

  4. “Experimental Mechanics of Nuclear Power Reactors,” by B. F. Langer, Westinghouse Electric Corp., Proceedings of the Society for Experimental Stress Analysis, XVII, No. 2, p. 97.

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Authors and Affiliations

  1. Brewer Engineering Laboratories, Inc., Marion, Mass.

    G. A. Brewer & J. D. Ingham

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  1. G. A. Brewer
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  2. J. D. Ingham
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Brewer, G.A., Ingham, J.D. Measurement of thermal stresses within an experimental nuclear-reactor vessel head. Experimental Mechanics 2, 9–14 (1962). https://doi.org/10.1007/BF02325805

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  • DOI: https://doi.org/10.1007/BF02325805

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