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    Dynamic Testing in Nuclear Power Plants for Model Validation

    Source: Journal of Dynamic Systems, Measurement, and Control:;1976:;volume( 098 ):;issue: 003::page 340
    Author:
    T. W. Kerlin
    ,
    E. M. Katz
    ,
    A. T. Chen
    ,
    J. G. Thakkar
    ,
    S. I. Chang
    DOI: 10.1115/1.3427047
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Dynamics tests were preformed at the Oconee pressurized water reactor to obtain information for checking a theoretical plant model. Low level, periodic reactivity perturbations were introduced and several system responses (reactor power, temperatures, pressures) were monitored. The data were processed off-line to give frequency responses. A linear state-variable model for the plant was formulated and used to compute theoretical frequency responses. A computerized, model-reference identification procedure was used to identify the fuel temperature coefficient of reactivity and the overall fuel-to-coolant heat transfer coefficient. The study showed that dynamic tests can be performed in operating nuclear power plants with insignificant interference to normal operation. Also, the use of automatic parameter identification procedures was demonstrated.
    keyword(s): Dynamic testing (Materials) , Model validation , Nuclear power stations , Temperature , Fuels , Frequency response , Industrial plants , Dynamics (Mechanics) , Coolants , Dynamic testing (Engineering) , Heat transfer coefficients AND Pressurized water reactors ,
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      Dynamic Testing in Nuclear Power Plants for Model Validation

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/88463
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    • Journal of Dynamic Systems, Measurement, and Control

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    contributor authorT. W. Kerlin
    contributor authorE. M. Katz
    contributor authorA. T. Chen
    contributor authorJ. G. Thakkar
    contributor authorS. I. Chang
    date accessioned2017-05-08T23:00:22Z
    date available2017-05-08T23:00:22Z
    date copyrightSeptember, 1976
    date issued1976
    identifier issn0022-0434
    identifier otherJDSMAA-26039#340_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/88463
    description abstractDynamics tests were preformed at the Oconee pressurized water reactor to obtain information for checking a theoretical plant model. Low level, periodic reactivity perturbations were introduced and several system responses (reactor power, temperatures, pressures) were monitored. The data were processed off-line to give frequency responses. A linear state-variable model for the plant was formulated and used to compute theoretical frequency responses. A computerized, model-reference identification procedure was used to identify the fuel temperature coefficient of reactivity and the overall fuel-to-coolant heat transfer coefficient. The study showed that dynamic tests can be performed in operating nuclear power plants with insignificant interference to normal operation. Also, the use of automatic parameter identification procedures was demonstrated.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleDynamic Testing in Nuclear Power Plants for Model Validation
    typeJournal Paper
    journal volume98
    journal issue3
    journal titleJournal of Dynamic Systems, Measurement, and Control
    identifier doi10.1115/1.3427047
    journal fristpage340
    journal lastpage347
    identifier eissn1528-9028
    keywordsDynamic testing (Materials)
    keywordsModel validation
    keywordsNuclear power stations
    keywordsTemperature
    keywordsFuels
    keywordsFrequency response
    keywordsIndustrial plants
    keywordsDynamics (Mechanics)
    keywordsCoolants
    keywordsDynamic testing (Engineering)
    keywordsHeat transfer coefficients AND Pressurized water reactors
    treeJournal of Dynamic Systems, Measurement, and Control:;1976:;volume( 098 ):;issue: 003
    contenttypeFulltext
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