Establishment and evaluation of reactor transient analyzing system for Kori Unit 3/4

The best-estimate(B-E) thermal-hydraulic programs, such as RETRAN, MARS and RELAP etc, are used only by a few experts due to the complexity involved in input preparation including control logic required for a realistic plant transient analysis. Korea Atomic Energy Research Institute has established 'Reactor Transient Analyzing System (RTAS)' for the purpose of easy use of B-E codes and effective EOP analysis without an additional control input for manual operation. RTAS, with features of an interactive manual control function and a plant mimic window, has a capability to simulate Emergency Operating Procedure (EOP) for Loss-of-Coolant Accident (LOCA) and Non-LOCA transients using MARS and RETRAN, respectively. In this study, the generation of input and Steam Generator Tube Rupture (SGTR) simulation for Kori-3/4 units based on EOP have been performed to evaluate the capability of RTAS and it is found that the-state-of-art simulation for SGTR is possible in an effective manner, with the basic input of RTAS