Algorithms and routines for determining thermal dynamics characteristics of WWER-440 reactor and primary coolant circuit

The method is described of developping algorithms for monitoring thermal dynamic characteristics of the reactor core and thermal hydraulic characteristics of the primary coolant circuit of a WWER 440 nuclear power plant. The routine written using the algorithms is shown and the results are reported obtained by their application during the physical and power start-up experiments on Unit I of the V-1 nuclear power plant. (author)