Development of nuclear reactor transient analyzer based on best-estimate codes, RETRAN and MARS

KAERI has developed a nuclear reactor transient analyzer based on the best-estimate system codes, RETRAN and MARS. The nuclear reactor transient analyzer consists of the best-estimate codes and the graphical user interface (GUI) for easy-to-use of these best-estimate codes. This paper presents various features of the GUI for nuclear reactor transient analyzer. The nuclear reactor transient analyzer is developed to assist all level of code users, ranging from beginner to experts, in their input preparations, code executions in a user-friendly basis, and output visualization to give an in-depth understanding of transient thermal-hydraulic behaviors in nuclear power plants. In addition, the interactive control function makes it possible to simulate operator actions during the transient simulation. This will extend its application to compact simulator