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    A Control Algorithm For Reactor Spatial Control During Nuclear Station Load Cycling

    Source: Journal of Dynamic Systems, Measurement, and Control:;1978:;volume( 100 ):;issue: 003::page 219
    Author:
    D. B. Cherchas
    ,
    C. G. Mewdell
    DOI: 10.1115/1.3426371
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A multivariable reactivity control algorithm is developed to maintain acceptable reactor spatial kinetics response during reactor power cycling. A modal model for describing the space-time kinetics response of a CANDU (Canadian Deuterium Uranium) reactor is devised and ultilized in the control study. A one neutron energy group approximation and other assumptions appropriate to the CANDU reactor studied are used to derive a diffusion equation from the linearized Boltzman equation. The effects of Xe135 and I135 are incorporated in the model. The kinetics variables are expanded in terms of an infinite series of eigenfunctions which are solutions of the scalar Helmholtz equation solved on the volume of the reactor. The control reactivities are modelled as an evenly distributed reactivity for gross reactor load cycling and point reactivity devices for spatial control. The system dynamics equations are written in a bilinear state space form. An algorithm is devised to determine the control vector required to achieve a desired kinetics behaviour about the nominal response. The algorithm is illustrated for a typical load cycle by means of a digital computer program.
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      A Control Algorithm For Reactor Spatial Control During Nuclear Station Load Cycling

    URI
    https://yetl.yabesh.ir/yetl1/handle/yetl/90894
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    • Journal of Dynamic Systems, Measurement, and Control

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    contributor authorD. B. Cherchas
    contributor authorC. G. Mewdell
    date accessioned2017-05-08T23:04:33Z
    date available2017-05-08T23:04:33Z
    date copyrightSeptember, 1978
    date issued1978
    identifier issn0022-0434
    identifier otherJDSMAA-26052#219_1.pdf
    identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/90894
    description abstractA multivariable reactivity control algorithm is developed to maintain acceptable reactor spatial kinetics response during reactor power cycling. A modal model for describing the space-time kinetics response of a CANDU (Canadian Deuterium Uranium) reactor is devised and ultilized in the control study. A one neutron energy group approximation and other assumptions appropriate to the CANDU reactor studied are used to derive a diffusion equation from the linearized Boltzman equation. The effects of Xe135 and I135 are incorporated in the model. The kinetics variables are expanded in terms of an infinite series of eigenfunctions which are solutions of the scalar Helmholtz equation solved on the volume of the reactor. The control reactivities are modelled as an evenly distributed reactivity for gross reactor load cycling and point reactivity devices for spatial control. The system dynamics equations are written in a bilinear state space form. An algorithm is devised to determine the control vector required to achieve a desired kinetics behaviour about the nominal response. The algorithm is illustrated for a typical load cycle by means of a digital computer program.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleA Control Algorithm For Reactor Spatial Control During Nuclear Station Load Cycling
    typeJournal Paper
    journal volume100
    journal issue3
    journal titleJournal of Dynamic Systems, Measurement, and Control
    identifier doi10.1115/1.3426371
    journal fristpage219
    journal lastpage226
    identifier eissn1528-9028
    treeJournal of Dynamic Systems, Measurement, and Control:;1978:;volume( 100 ):;issue: 003
    contenttypeFulltext
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    DSpace software copyright © 2002-2015  DuraSpace
    نرم افزار کتابخانه دیجیتال "دی اسپیس" فارسی شده توسط یابش برای کتابخانه های ایرانی | تماس با یابش
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