The Relative Power Contribution methodology has been applied to delineate the initiating event leading to a BWR transient. Diverse reactor signals were analyzed to calculate the coefficients required on the relative power contribution method. Those coefficients were computed from an autoregressive multivariable model. Among the signals used in the analysis of the transient event are total flow through the core, pressure drop across the core, feedwater flow, and reactor power. Analyses of the same type of transient event showed a resonance of the main event frequency on the range within which it has been considered and observed frequencies related to some failures of certain control systems of a nuclear power plant. Those analyses employed the short-time Fourier transform or the power spectral density, for time-frequency and frequency-only domains, respectively. In this work, the same value of the frequency of the resonance mentioned above was obtained through the relative power contribution analysis, but, furthermore it was found that the feedwater flow behavior had an important impact on the transient event, and also that the transient event was not initiated by a reactivity-related instability.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Application of the Relative Power Contribution Methodology to the Analysis of a Control System Failure Available to Purchase
Rogelio Castillo-Dura´n,
Rogelio Castillo-Dura´n
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Search for other works by this author on:
Javier Ortiz-Villafuerte,
Javier Ortiz-Villafuerte
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Search for other works by this author on:
Rodolfo Amador-Garci´a,
Rodolfo Amador-Garci´a
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Search for other works by this author on:
Edmundo del-Valle-Gallegos,
Edmundo del-Valle-Gallegos
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Search for other works by this author on:
Javier C. Palacios-Herna´ndez,
Javier C. Palacios-Herna´ndez
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Search for other works by this author on:
Gabriel Calleros-Micheland
Gabriel Calleros-Micheland
Comisio´n Federal de Electricidad, Alto Lucero, Ver., Me´xico
Search for other works by this author on:
Rogelio Castillo-Dura´n
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Javier Ortiz-Villafuerte
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Rodolfo Amador-Garci´a
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Edmundo del-Valle-Gallegos
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Javier C. Palacios-Herna´ndez
Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Me´x., Me´xico
Gabriel Calleros-Micheland
Comisio´n Federal de Electricidad, Alto Lucero, Ver., Me´xico
Paper No:
ICONE17-75866, pp. 187-191; 5 pages
Published Online:
February 25, 2010
Citation
Castillo-Dura´n, R, Ortiz-Villafuerte, J, Amador-Garci´a, R, del-Valle-Gallegos, E, Palacios-Herna´ndez, JC, & Calleros-Micheland, G. "Application of the Relative Power Contribution Methodology to the Analysis of a Control System Failure." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 187-191. ASME. https://doi.org/10.1115/ICONE17-75866
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Pressure Estimation From Oscillatory Signals Obtained Through BWR’s Instrument Lines
J. Dyn. Sys., Meas., Control (March,1986)
Signal Validation for Nuclear Power Plants
J. Dyn. Sys., Meas., Control (March,1983)
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Related Chapters
Constructing Dynamic Event Trees from Markov Models (PSAM-0369)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Assessment of Depression from Speech
International Conference on Mechanical and Electrical Technology, 3rd, (ICMET-China 2011), Volumes 1–3
LOCA Frequencies Estimated from Operating Experience (PSAM-0282)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)