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    Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

    Source: Journal of Pressure Vessel Technology:;1991:;volume( 113 ):;issue: 003::page 349
    Author:
    G. L. Stevens
    ,
    S. Ranganath
    DOI: 10.1115/1.2928766
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: 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.
    keyword(s): Fatigue , Life extension , Nuclear reactors , Industrial plants , Stress , Temperature , Computers , Boiling water reactors , Monitoring systems , Functions , Nozzles , Power stations , Pressure , Flow (Dynamics) , Feedwater , Stress analysis (Engineering) AND Finite element analysis ,
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      Use of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension

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    http://yetl.yabesh.ir/yetl1/handle/yetl/109030
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    contributor authorG. L. Stevens
    contributor authorS. Ranganath
    date accessioned2017-05-08T23:36:19Z
    date available2017-05-08T23:36:19Z
    date copyrightAugust, 1991
    date issued1991
    identifier issn0094-9930
    identifier otherJPVTAS-28329#349_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/109030
    description abstractThe 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.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleUse of On-Line Fatigue Monitoring of Nuclear Reactor Components as a Tool for Plant Life Extension
    typeJournal Paper
    journal volume113
    journal issue3
    journal titleJournal of Pressure Vessel Technology
    identifier doi10.1115/1.2928766
    journal fristpage349
    journal lastpage357
    identifier eissn1528-8978
    keywordsFatigue
    keywordsLife extension
    keywordsNuclear reactors
    keywordsIndustrial plants
    keywordsStress
    keywordsTemperature
    keywordsComputers
    keywordsBoiling water reactors
    keywordsMonitoring systems
    keywordsFunctions
    keywordsNozzles
    keywordsPower stations
    keywordsPressure
    keywordsFlow (Dynamics)
    keywordsFeedwater
    keywordsStress analysis (Engineering) AND Finite element analysis
    treeJournal of Pressure Vessel Technology:;1991:;volume( 113 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
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