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Study on generalized predictive control for the neutron flux density of the nuclear reactor

Research output: Contribution to journalArticlepeer-review

Abstract

The mathematical model of the neutron dynamic system of the nuclear reactor was transformed into a sort of controlled auto-regressive integrated moving average (CARIMA) model. A generalized predictive control method for the neutron flux density was developed. This new control strategy can efficiently eliminate the influence of uncertain perturbations and non-linearity and can enhance control precision and dynamic qualities of the system. The advantages over the classical control methods are demonstrated by computer simulation.

Original languageEnglish
Pages (from-to)340-344
Number of pages5
JournalYuanzineng Kexue Jishu/Atomic Energy Science and Technology
Volume37
Issue number4
StatePublished - Jul 2003

Keywords

  • Computer simulation
  • Generalized predictive control
  • Neutron flux density
  • Nuclear reactor

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