On the dependence of the noise amplitude on the correlation length of inlet temperature fluctuations in PWRs

Zylbersztejn, Florian; Tran, Hoai-Nam; Pázsit, Imre; Demazière, Christophe; Nylén, Henrik

doi:10.1016/j.anucene.2013.01.057

Cited by 10 publications

(2 citation statements)

References 5 publications

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“…The development and/or application of time-series-analysis and system identification techniques dedicated to instrumentation, monitoring and diagnostics of Light-Water-Reactor (LWR) processes or for inference of physical mechanisms from the latter, has been and continues to be a matter of intensive research (Williams, 1977;Fry et al, 1984;Sweeney et al, 1987;Pazsit, 1999;Zylbersztejn et al, 2013). For Boiling-Water-Reactors (BWRs), a specific and important target application of time-series-analysis that can be mentioned is the evaluation of the reactor stability properties using measured neutron flux signals as basis.…”

Section: Introductionmentioning

confidence: 99%

Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event

Demeshko

Dokhane

Washio

et al. 2015

Annals of Nuclear Energy

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Discrete and continuous time signals Reactor noise and causality analysis BWR stability and dynamics a b s t r a c t This paper presents a first application of a novel Continuous and Structural Autoregressive Moving Average (CSARMA) modeling approach to BWR noise analysis. The CSARMA approach derives a unique representation of the system dynamics by more robust and reliable canonical models as basis for signal analysis in general and for reactor diagnostics in particular. In this paper, a stability event that occurred in a Swiss BWR plant during power ascension phase is analyzed as well as the time periods that preceded and followed the event. Focusing only on qualitative trends at this stage, the obtained results clearly indicate a different dynamical state during the unstable event compared to the two other stable periods. Also, they could be interpreted as pointing out a disturbance in the pressure control system as primary cause for the event. To benchmark these findings, the frequency-domain based signal transmission-path (STP) method is also applied. And with the STP method, we obtained similar relationships as mentioned above. This consistency between both methods can be considered as being a confirmation that the event was caused by a pressure control system disturbance and not induced by the core. Also, it is worth noting that the STP analysis failed to catch the relations among the processes during the stable periods, that were clearly indicated by the CSARMA method, since the last uses more precise models as basis.

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Section: Introductionmentioning

confidence: 99%

Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event

Demeshko

Dokhane

Washio

et al. 2015

Annals of Nuclear Energy

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“…This region has been studied for surveillance purposes and for detecting core flow anomalies in several papers [10,11,14,15]. This frequency range coincides with the frequency of maximum response to thermohydraulic oscillations, the heat transfer processes as well as the moderator temperature coefficient (MTC) feedback [2,3,16,17]. The relationship of neutron noise behaviour and thermohydraulic oscillations has been addressed in several studies, where simulations of scenarios that consider flow and temperature oscillations have been analysed ( [18][19][20].…”

Section: Introductionmentioning

confidence: 99%

Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core

Barrio-Parra

Chionis

Montalvo

et al. 2019

Annals of Nuclear Energy

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KWU-PWR plants show a high level of neutron noise that usually represents added problems in their operation. The frequency region of interest is below 1 Hz, so that thermohydraulic oscillations seem to be one of the main reasons behind. Nevertheless, recently, the neutron noise has experienced an increase in its normalized root mean square that coincide in time with the introduction of a new design of fuel assembly. This fact points out that there should be some relationship between neutron noise spectral characteristics and fuel assemblies' performance. In order to advance in understanding this phenomenon, the transient nodal code SIMULATE-3K (S3K) has been used to simulate mechanical vibrations of fuel assemblies and thermohydraulic oscillations of the core inlet flow. The simulated results obtained are neutron detectors signals which are analysed with noise analysis techniques and compared to real data.

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Research on Improvement of C2 Signal Alarm in Nuclear Instrument System of PWR Nuclear Power Plant

Li,

Jin,

Zhang

2024

Lecture Notes in Electrical Engineering

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On the dependence of the noise amplitude on the correlation length of inlet temperature fluctuations in PWRs

Cited by 10 publications

References 5 publications

Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event

Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event

Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core

Research on Improvement of C2 Signal Alarm in Nuclear Instrument System of PWR Nuclear Power Plant

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