Analysis of Computer Code and Method Used in Thermal-Hydraulic Safety Justification of VVER Reactor Plants
This article presents the analysis of the calculation procedure and computer code KLAST used in calculations of the control rod dynamic characteristics during safety justification of water-cooled water-moderated power reactor plants. The code allows accounting for pressure differentials as a function of time occurred under the design conditions on the reactor core and on the drive extension shaft as well change of coolant density in the core.