Universal Dynamic Model of RBMK Reactor As a Tool for Safety Analysis and Severe Accidents Management. Its Reliability and Validation

The paper is to specify the developed in RRC Kurchatov Institute mathematical model and the integrated STEPAN/KOBRA code for the RBMK power units dynamics modeling focusing on specifying this integrated code as a tool with applications for safety analysis and the operators training into power unit control under severe accidents conditions. Therewith, the main accent centers on the reliability of mathematical models and both the integrated code and the codes incorporated into this code. Presented are the code, its constituents, and provided is the review of their validation results. To complement the general review, the most sensitive of such results are hereby set forth in the paper. Provided also is the basic list of severe accidents reproduced through using the full scope LNPP simulators, which conditions serve to foster the correct performance actions by the power units personnel during the training sessions. (authors)