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A Stochastic Method for Nuclear Power Plant Diagnosis

  • R. B. Perez
  • R. T. Wood

Abstract

The value of using neutron noise descriptors, especially the power spectral densities (PSDs) of ex-core detectors, to monitor core barrel motion and fuel element vibrations in pressurized water reactors (PWRs) is well established.1–6 Indeed, in the mid-frequency range (1–20 Hz), PWR neutron noise is dominated by vibration peaks in the neutron PSD that result from the motion of reactor internals. A qualitative examination of such descriptors from a 1150 MWE Westinghouse PWR plant, revealed significant changes in the plant’s noise signature (PSD) as its first fuel cycle proceeded. The purpose of this work is to use a mathematical model of the interaction between small mechanical motions and the core neutronics to provide a tool for quantitative investigation of the PSD structure in the vibrational frequency range.7

Keywords

Power Spectral Density Fuel Element Fuel Assembly Fuel Cycle Neutron Detector 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

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    J. March-Leuba, G. de Saussure, and R. B. Perez Trans. Am. Nucl. Soc. 44 (1983).Google Scholar

Copyright information

© Plenum Press, New York 1989

Authors and Affiliations

  • R. B. Perez
    • 1
    • 2
  • R. T. Wood
    • 1
    • 2
  1. 1.The University of TennesseeKnoxvilleUSA
  2. 2.Oak Ridge National LaboratoryOak RidgeUSA

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