Noise signals at the output of the technological parameters of a nuclear power plant (neutron flux, dynamic pressure, etc.) contain important information on the stale of the equipment. Effective algorithms have been developed for identifying random processes which, after appropriate transformation, are treated as multidimensional random vectors. These vectors are automatically classified by means of the aforementioned algorithms on the basis of the likelihood function, in particular, of the Bayesian classifier and resolving functions. The use of the Bayesian classifier is based on constructing multidimensional distributions of probabilities in the attribute space with the applicable dimensionality, which serves to describe random representing vectors of the applicable images that are subject to automatic classification.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4243-6
PROCEEDINGS PAPER
A Methodology for Discerning Incipient Boiling of the Coolant in a Water-Moderated, Water-Cooled (Pressurized-Water) Nuclear Reactor by Means of the Bayesian Neutron-Noise Classifier
Igor Sharayevskij
Igor Sharayevskij
National Academy of Sciences of Ukraine, Kiev, Ukraine
Search for other works by this author on:
Igor Sharayevskij
National Academy of Sciences of Ukraine, Kiev, Ukraine
Paper No:
ICONE14-89630, pp. 661-668; 8 pages
Published Online:
September 17, 2008
Citation
Sharayevskij, I. "A Methodology for Discerning Incipient Boiling of the Coolant in a Water-Moderated, Water-Cooled (Pressurized-Water) Nuclear Reactor by Means of the Bayesian Neutron-Noise Classifier." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 2: Thermal Hydraulics. Miami, Florida, USA. July 17–20, 2006. pp. 661-668. ASME. https://doi.org/10.1115/ICONE14-89630
Download citation file:
5
Views
Related Proceedings Papers
Related Articles
Sequential Testing for Fault Detection in Multiply-Redundant Systems
J. Dyn. Sys., Meas., Control (June,1989)
CANDU Reactor Space-Time Kinetic Model for Load Following Studies
J. Eng. Gas Turbines Power (May,2011)
Stochastic Averaging and Optimal Prediction
J. Vib. Acoust (December,2007)
Related Chapters
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Reactor Shutdown and Reactor Restart
Fundamentals of CANDU Reactor Physics
Regional/Neutron Overpower Protection (ROP/NOP)
Fundamentals of CANDU Reactor Physics