Abstract
This article describes the mathematical apparatus for express analysis of the archive of operational parameters. The developed algorithms based on the methods of reducing the dimension of the space of variables and the “Chernoff Faces” method allow visualizing the dynamics of changes in generalized limiting parameters, as well as visually determining the approximation or intersection of permitted values by parameters, which in turn can provide scientific and practical use in improving quality of operational personnel work and analysis of situations requiring additional attention and more detailed analysis.
Highlights
The safe operation of powerful nuclear power reactors is ensured by the availability of information and computer systems that make it possible to measure, calculate and control the most important parameters of a nuclear power unit [1,2,3,4]
At power units with RBMK reactors such a system is called “SKALA”, which allows controlling about 10,000 parameters in almost real time mode. This information is partially visualized on a unit control board and enables operators to efficiently and safely manage a nuclear power unit
It would be desirable to visualize the generalized parameters of a nuclear power unit containing the most important information about the technological process in the integral
Summary
The safe operation of powerful nuclear power reactors is ensured by the availability of information and computer systems that make it possible to measure, calculate and control the most important parameters of a nuclear power unit [1,2,3,4]. At power units with RBMK reactors such a system is called “SKALA”, which allows controlling about 10,000 parameters in almost real time mode. This information is partially visualized on a unit control board and enables operators to efficiently and safely manage a nuclear power unit. In addition to the functions of directly providing information for the operational management of the technological process, the information and computer complex archives the current measured and calculated parameters This enables a posteriori analysis of the quality of process control in order to obtain new scientific and practical results. Identification of reasons of separate items of reactor core and main technological equipment break down (solving problems of predictive analytics)
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