MARS-KS Assessment of TRACE Fundamental Problems

MARS(Multi-dimensional Analysis of Reactor Safety) code has been developed for the realistic multidimensional thermal-hydraulic system analysis of light water reactor transients. In this study, the phenomenological problems were used to determine whether the code produces qualitatively correct results. The main objectives of this study were to offer the additional validation data of MARS code by solving TRACE fundamental test problems. A total of five simple problems were used to evaluate the MARS code. This study is to investigate base capabilities of MARS for predicting the behavior of nuclear power plant. For this investigation, comparing code predictions against experimental data and the physics were conducted