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RISContributions of the ORNL Piping Program to Nuclear Piping Design Codes and Standards
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Since 1967, ORNL Piping Program has been engaged in providing information for the development of stress indices to be used in the analysis of piping components for nuclear power plants. This ...
Background for Changes in the 1981 Edition of the ASME Nuclear Power Plant Components Code for Controlling Primary Loads in Piping Systems
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Section III of the ASME Boiler and Pressure Vessel Code contains simplified design formulas for placing bounds on the plastic deformations in nuclear power plant piping systems. For Class 1 ...
Experimental Stress Analysis for Four 24-in. ANSI Standard B16.9 Tees
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper describes the experimental stress analysis of low cycle fatigue tests of four tees tested by Combustion Engineering, Inc. (C-E) under subcontract to Union Carbide Nuclear Division. ...
Effective Stress Factor Correlation Equations for Piping Branch Junctions Under Internal Pressure Loading
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The results from a previous finite element parametric study by the authors on the effective stress factors (ESFs) occurring in piping branch junctions under internal pressure loading are used ...