Abstract
PCTran is a fast PC-based nuclear power plant simulation code developed by Taiwan Power Company (TPC) and Micro-Simulation Technology. We used it to simulate various transients and events in order to assess the safety of nuclear power plants. In the present thesis, we tried to use PCTran for Maanshan to simulate and compare ten cases chosen from Final Safety Analysis Report (FSAR). The results will provide us the capabilities and prediction performances of PCTran. In the thesis, we first introduce the main functions of PCTran and examine initial conditions and physical parameters in FSAR cases. After that, we decide and setup associated best initial conditions, malfunctions, and other actions in PCTran, and execute. After intensive comparisons between PCTran simulations and FSAR, we noticed that all cases involved in secondary loop transients showed good agreements. On the other hand, the primary side transients indicated higher-than-FSAR cladding temperatures, probably due to inadequacies of ECCS models in PCTran. Some parameters like DNBR and LVPZ in the study are quite different from the results of FSAR. In addition, there are no appropriate models in PCTran to simulate the cases involving steam generator feedwater line break.