Development of Kartini Reactor Code to Support Nuclear Training Center and Safety Analysis

Abstract

Development of a 100 kW Kartini research reactor code was carried out to support Nuclear Training Center and reactor safety analysis. The code has abilities of both simulating normal and abnormal conditions of the reactor. It was developed based on interaction among governing equations of mass and energy conservations, fuel rod heat conduction, and point kinetics. For simplicity, the code considers only one type of control rod rather than three types of control rods as used in the reactor. Calculation results of the power and axial coolant temperature distribution at rated power show a sufficient agreement with those of experimental data. Results of the plant dynamics analysis by using the code also show a correct plant's behavior as those of general light water reactors. Rough safety analysis of an excess reactivity insertion was carried out and the calculation results show that the limit of reactor safety is satisfied. It might improve the code by consideration of three types of control rods to decrease the calculation errors. However, the code was satisfied to be used as a tool for both supporting the nuclear training center and safety analysis.