The application of an on-line fatigue monitoring system for tracking fatigue usage in operating power plants is described. The system, like several others which have been developed, uses the influence function approach, operates on a microcomputer, and determines component stresses using temperature, pressure, and flow rate data that are typically available from plant computers. Using plant-unique influence functions developed specifically for each component location, the system calculates stresses as a function of time and computes the fatigue usage. Stress values are calculated at time intervals defined by the user and the fatigue values are saved on files for use at a later time. The application of the GE Fatigue Monitoring System (GEFMS) to calculate fatigue usage in the feedwater nozzle of a GE Boiling Water Reactor is described in this paper. Stress predictions using GEFMS for a sample temperature transient show excellent agreement with results from finite element thermal and stress analysis performed on a mainframe computer. Fatigue usage calculations for a simulated 24-hr temperature record confirm that the system provides accurate results at a cost that is significantly lower than similar analysis done on mainframe computer systems. The system, which has been installed in a boiling water reactor plant, provides the technical basis to evaluate actual reactor conditions and justify plant life extension.
Skip Nav Destination
Article navigation
August 1991
Research Papers
Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension
G. L. Stevens,
G. L. Stevens
Materials Monitoring and Structural Analysis Services, GE Nuclear Energy, San Jose, CA 95125
Search for other works by this author on:
S. Ranganath
S. Ranganath
Materials Monitoring and Structural Analysis Services, GE Nuclear Energy, San Jose, CA 95125
Search for other works by this author on:
G. L. Stevens
Materials Monitoring and Structural Analysis Services, GE Nuclear Energy, San Jose, CA 95125
S. Ranganath
Materials Monitoring and Structural Analysis Services, GE Nuclear Energy, San Jose, CA 95125
J. Pressure Vessel Technol. Aug 1991, 113(3): 349-357 (9 pages)
Published Online: August 1, 1991
Article history
Received:
September 5, 1989
Revised:
December 28, 1990
Online:
June 17, 2008
Citation
Stevens, G. L., and Ranganath, S. (August 1, 1991). "Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension." ASME. J. Pressure Vessel Technol. August 1991; 113(3): 349–357. https://doi.org/10.1115/1.2928766
Download citation file:
Get Email Alerts
Cited By
The Behavior of Elbow Elements at Pure Bending Applications Compared to Beam and Shell Element Models
J. Pressure Vessel Technol (February 2025)
Related Articles
Finite Element Based Full-Life Cyclic Stress Analysis of 316 Grade Nuclear Reactor Stainless Steel Under Constant, Variable, and Random Fatigue Loading
J. Pressure Vessel Technol (October,2018)
Analysis of Feedwater Pump Suction Pressure Decay Under Instant Turbine Load Rejection
J. Eng. Power (April,1972)
Protection of Boiler Feed Pump Against Transient Suction Pressure Decay
J. Eng. Power (July,1974)
Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor
J. Pressure Vessel Technol (April,2012)
Related Proceedings Papers
Related Chapters
Fatigue Verification and Nonlinear Alternatives
Toward Consistent Design Evaluation of Nuclear Power Piping by Nonlinear Finite Element Analysis
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
IWE and IWL
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes