Influence of feedback on the MTC estimate by noise analysis

Griet Monteyne, Peter Baeten, Johan Schoukens

    Research outputpeer-review

    1 Scopus citations

    Abstract

    This article discusses the influence of feedback on the Moderator Temperature Coefficient (MTC) estimate by a noise analysis method. Until now feedback was considered to be negligible in the frequency band of interest. However measurements at a Belgian Nuclear Power Plant will be used to show that the influence of feedback on the MTC estimate is not negligible in the frequency band of interest. This makes the analysis difficult since the presence of feedback creates systematic errors in the MTC estimate unless special experimental conditions can be realized. The theoretical analysis will explain how the most used non-parametric estimation of the MTC is influenced by the presence of the feedback. For the explanation we will consider a simplified scheme of the MTC measurement setup with feedback. The theory will be verified by simulations in MATLAB. For the verification we consider a simplified system captured in a feedback loop. We will estimate the system for different situations. It will be seen that the non-parametric system estimate is only unbiased when the signal that is fed back to the input is negligible in comparison with the reference signal. Since the feedback is not negligible in practice, special experimental conditions are required to obtain an unbiased non-parametric MTC estimate.

    Original languageEnglish
    Title of host publication7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010
    Pages662-669
    Number of pages8
    Volume1
    StatePublished - 2010
    Event2010 - 7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010 - Las Vegas, NV
    Duration: 7 Nov 201011 Nov 2010

    Publication series

    Name7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010
    Volume1

    Conference

    Conference2010 - 7th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2010, NPIC and HMIT 2010
    Country/TerritoryUnited States
    CityLas Vegas, NV
    Period2010-11-072010-11-11

    ASJC Scopus subject areas

    • Human-Computer Interaction
    • Nuclear Energy and Engineering
    • Control and Systems Engineering

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