scholarly journals Development of field programmable gate array–based encryption module to mitigate man-in-the-middle attack for nuclear power plant data communication network

2018 ◽  
Vol 50 (5) ◽  
pp. 780-787 ◽  
Author(s):  
Mohamed Abdallah Elakrat ◽  
Jae Cheon Jung
2019 ◽  
Author(s):  
Restu Maerani ◽  
Arya Adhyaksa Waskita ◽  
Satrio Pradana ◽  
Saharudin ◽  
Deswandri ◽  
...  

2007 ◽  
Author(s):  
Miljko Bobrek ◽  
Don Bouldin ◽  
David Eugene Holcomb ◽  
Stephen M Killough ◽  
Stephen Fulton Smith ◽  
...  

2015 ◽  
Vol 137 (6) ◽  
Author(s):  
Annalisa Perasso ◽  
Cristina Campi ◽  
Cristian Toraci ◽  
Francesco Benvenuto ◽  
Michele Piana ◽  
...  

This paper describes a classification method for automatic fault detection in nuclear power plant (NPP) data. The method takes as input time series associated to specific parameters and realizes signal classification by using a clustering algorithm based on possibilistic C-means (PCM). This approach is applied to time series recorded in a CANDU® power plant and is validated by comparison with results provided by a classification method based on principal component analysis (PCA).


Author(s):  
Li-Ling Zhu ◽  
Bin Wu ◽  
Gang Li ◽  
Yi-Qin Xie ◽  
Yong-Bin Sun

Because of the rapid changes that are taking place in the digital computer and the graphic display technology employed in a modern human system interface, the use of integrated digital display devices to replace traditional instruments has become a new application tendency in nuclear power plant. The safety control and display device (refer as to SCID hereafter) is a safety class digital Human System Interface (HSI) device of FirmSys platform. It provides display and control function of the safety system in ACPR1000 nuclear power plant. This paper mainly introduces the typical application architecture of SCID in ACPR1000 NPP, the main functions (including control and display function, application mode management function, data processing function and data communication function) of SICD and the innovation and improvement of SCID. The application of SCID has improved the integration of the HMI system and reduced the workload of the operating staff. It has been successfully applied in several ACPR1000 nuclear power plants.


Author(s):  
Jonathan A. Cumming ◽  
Michael Goldstein

This article discusses the results of a study in Bayesian analysis and decision making in the maintenance and reliability of nuclear power plants. It demonstrates the use of Bayesian parametric and semiparametric methodology to analyse the failure times of components that belong to an auxiliary feedwater system in a nuclear power plant at the South Texas Project (STP) Electric Generation Station. The parametric models produce estimates of the hazard functions that are compared to the output from a mixture of Polya trees model. The statistical output is used as the most critical input in a stochastic optimization model which finds the optimal replacement time for a system that randomly fails over a finite horizon. The article first introduces the model for maintenance and reliability analysis before presenting the optimization results. It also examines the nuclear power plant data to be used in the Bayesian models.


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