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Core Monitoring

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Reactor Core Monitoring

Part of the book series: Lecture Notes in Energy ((LNEN,volume 58))

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Abstract

Reactor parameters subjected to limitations are continually monitored. Reactor operation is based on a number of parameters characterizing the distribution of coolant temperature, power profiles in the fuel assemblies, power density distribution. In-core instrumentation supplies raw data, which are processed, and finally reactor operator is provided with maps and logs. The present chapter describes detection methods, the elaboration of the detector signals, and the main steps of signal processing. The presented methods are used typically in pressurized water reactors (PWRs) and boiling water reactors. The emphasis is on the applied mathematical and physical methods as well as considerations.

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Notes

  1. 1.

    The in-core system samples the data with cycle time \(\sim \)1 s, so the reactor can be considered as stationary most of the time.

  2. 2.

    The equations to be quoted below refer to assembly No. i, added as a subscript to the corresponding expression.

  3. 3.

    Yet we preserve the traditional notation Q although it is a random variable.

  4. 4.

    Henceforth we use the term SPND for both measurements.

  5. 5.

    Extrapolated upper and lower end of the axial power profile.

  6. 6.

    The mentioned data are in the fuel passport .

  7. 7.

    Detailed discussion of probability distributions is available in symbolic mathematics and statistics softwares like MATHEMATICA, MATLAB, MAPLE etc.

  8. 8.

    That number is called confidence level .

  9. 9.

    Here we deal only with normal operation.

  10. 10.

    As far as the authors note, it has happened that to reduce the irradiation of the rector vessel, a VVER-440/213 core geometry has been changed.

  11. 11.

    Note that from 100 points two or three points always fall outside the \(3\sigma \) limit.

  12. 12.

    A lucky analyst may have a document where the concept is clearly formulated.

  13. 13.

    Actually, the data serve comparing measured and calculated values.

  14. 14.

    Fuel damage as used here is defined as penetration of the fission products barrier (i.e. the fuel rod clad).

  15. 15.

    SCRAM-System Control Rod Automatic Motion.

  16. 16.

    This is especially important when there are assemblies with burning poison in the core.

  17. 17.

    This depends on the goal of the calculation. A number of codes put up with one an initial enrichment and one burnup level, others may require a number of fissionable isotopes or fission products.

  18. 18.

    Burnup varies very slowly in time.

  19. 19.

    On a similar other leaflet PWR.

  20. 20.

    Usually less than 30 s are needed for a full core 3-dimensional SIMULATE-3 calculation.

  21. 21.

    The original notation has been retained.

  22. 22.

    LAN = Local Area Network.

  23. 23.

    Term regular and irregular mesh is also used.

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  1. Budapest, Hungary

    Mihály Makai

  2. Alkmaar, The Netherlands

    János Végh

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Makai, M., Végh, J. (2017). Core Monitoring. In: Reactor Core Monitoring. Lecture Notes in Energy, vol 58. Springer, Cham. https://doi.org/10.1007/978-3-319-54576-9_2

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