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Using model-based fault detection to differentiate transients and loss of coolant accidents

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

In the nuclear power industry, one important class of accidents is the loss of coolant accident (LOCA). This paper presents methods to detect a LOCA that is initiated: (i) while the plant is going through a small transient, and (ii) with a time-varying leak magnitude. The accident is simulated using a generic pressurized water reactor (GPWR) simulator. The fault is detected using a model-based approach with models identified using GPWR data. The model-based approach is multiple-model adaptive estimation (MMAE), which uses multiple system models representing both normal and faulted operating conditions. During operation, these models simulate the potential operating conditions, incorporating measurement feedback in a Kalman filter state-estimation structure. Faults are detected by selecting the model that most closely matches the system according to statistical characteristics. For a LOCA, data-driven models of the pressurizer liquid level are derived using first-principles and system identification. In system identification, a physics-based model form is derived that contains unknown parameters. System identification is then used to estimate the parameter values based on measurement data, providing plant-specific pressurizer models. For the accident scenario described above, the proposed methods differentiate between the transient and the accident, and provide real-time estimates of the leak magnitude after it has been initiated.

Original languageEnglish
Title of host publication11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019
PublisherAmerican Nuclear Society
Pages868-878
Number of pages11
ISBN (Electronic)9780894487835
StatePublished - 2019
Externally publishedYes
Event11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019 - Orlando, United States
Duration: Feb 9 2019Feb 14 2019

Publication series

Name11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019

Conference

Conference11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2019
Country/TerritoryUnited States
CityOrlando
Period02/9/1902/14/19

Keywords

  • Loss of coolant accident
  • Model-based online monitoring
  • System identification

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