Application of RELAP5-3D Code for RBMK-1500 Transient Analysis

摘要

The RELAP5-3D code was originally designed for PWR type reactors to provide the analytical tool for the independent evaluation of the reactor safety through the mathematical simulation of transients and accidents. This code has been used since 1999 in the Lithuanian Energy Institute. The code has been adapted to simulate the RBMK type reactors. This paper presents the benchmark of the operational transients, which took place at the only Lithuanian nuclear power plant ― Ignalina NPP, using the integrated thermal-hydraulics-neutronics model.