The cross-analysis method is an indispensable part of scientific investigations and human activities. Basically, the mathematical background of these methods does not depend on the chosen field of application. In the current document, the fusion facility is chosen.
The COMPASS-U tokamak, a high-magnetic field (5 T) device, will be capable of developing and testing innovative and reactor-relevant divertor configurations for efficient plasma end energy exhaust at high plasma density and in an all-metal environment. In addition, advanced confinement regimes promising for the ITER and DEMO tokamaks will be studied in relevant conditions. Especially, the operation with hot first walls as in future reactors will represent a unique feature of COMPASS-U.
At the current time, the integral method of the cross-correlation analysis is one of the main focuses of the data analysis on fusion facilities. However, such methods can be applied not only in fusion, but also in different fields of human activities connected with analyzing the different data fluxes. As a source of the diagnostic data, the COMPASS (Prague, Czech Republic), SMART (Seville, Spain), and KSTAR (Daejeon, Korea) are planned to be used.
A mutual collaboration between Czech, Spanish, and Korean research institutions on real-time plasma diagnostics will provide the concept of unique integrated methods in combination with the real-time measurement algorithms that can be applied on the modern fusion facilities, as well as in different fields of human activities. For instance, this concept can also be useful for ITER and DEMO.