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

•Low frequency Neutron noise in KWU reactors is higher than in other reactors.•Both mechanical and thermal-hydraulic perturbations at the core inlet are simulated with S3K.•The results of the simulations are analyzed with noise analysis techniques.•Comparison with real data is also included.•The spe...

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Bibliographic Details
Published in:Annals of nuclear energy 2019-04, Vol.126, p.242-252
Main Authors: Torres, L.A., Chionis, D., Montalvo, Cristina, Dokhane, A., García-Berrocal, A.
Format: Article
Language:English
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Summary:•Low frequency Neutron noise in KWU reactors is higher than in other reactors.•Both mechanical and thermal-hydraulic perturbations at the core inlet are simulated with S3K.•The results of the simulations are analyzed with noise analysis techniques.•Comparison with real data is also included.•The spectral characteristics of neutron noise seem to be related to both mechanical and thermal-hydraulic perturbations. KWU pre-Konvoi PWRs (SIEMENS design) are commonly exhibiting high neutron noise levels which can lead to costly operational issues (i.e. activation of SCRAM system, operation of unrated core power, etc.). The frequency region of interest of neutron noise is below 1 Hz, which is the typical frequency range of thermal-hydraulic phenomena. This feature seems to indicate that, coolant flow and temperature oscillations can have a key impact on neutron noise phenomena. Moreover, an increasing neutron noise trend (in term of normalized root mean square) was recently observed in many KWU-PWRs. This increasing trend has been speculated to be correlated with the introduction of a new fuel design type in the KWU-PWRs. This fact indicates that there should be some correlation 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 thermal-hydraulic fluctuations of the core inlet flow and temperature. The simulated neutron detectors responses are analysed with noise analysis techniques and compared to real plant data. This analysis indicates that the cross-feedback between the mechanical and thermal-hydraulic disturbances complicate the identification of the origin of the perturbation source. The simulated results indicate that the neutron noise spectral characteristics can be associated separately to different causes. In this sense, the results of this work seem to indicate that the spectral features of the neutron noise are a consequence of both mechanical perturbations and thermal-hydraulic fluctuations.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2018.11.032