抄録
Kuosheng Nuclear Power Plant (NPP) is located on the northern coast of Taiwan. Its nuclear steam supply system is a type of BWR/6 designed and built by General Electric. There were three main steps in this study. First, Kuosheng NPP TRACE/SNAP model was developed in this research. The containment was also simulated in this model. In order to assess the system response of the Kuosheng NPP TRACE/SNAP model, this study used startup tests data (load rejection and a feedwater pump trip transients) to compare with the results of TRACE. Second, the transient analysis of Kuosheng NPP TRACE/SNAP model under Fukushima-like (SBO) or more severe (SBO+LOCA) conditions was performed. Third, in order to confirm the mechanical property and integrity of fuel rods, FRAPTRAN analysis was also performed in this study. In the comparison of startup tests and TRACE data, the results and sequences of TRACE were similar to startup tests data. By the above compared results, it indicated that there was a respectable accuracy in Kuosheng NPP TRACE/SNAP model. In SBO transient (no water injection case) analysis, the PCT (peak cladding temperature) was larger than 1088.7 K at 4730 sec which indicated that the zirconium-water reaction was able to generate. In SBO + LOCA transient (no water injection case), PCT reached the criteria of 1088.7 K at 1900 sec and FRAPTRAN results implied that the fuel rod burst at 2000 sec. However, if the fire water (flow rate 39 kg/sec) injected to the reactor at 800 sec in this transient, TRACE results depicted that PCT was lower than 1088.7 K and FRAPTRAN results also indicated that the integrity of fuel rod was kept. But one safety issue generated in the drywell during 1460〜2570 sec due to the drywell temperature larger than the limit (438.71 K). Finally, TRACE/SNAP analysis results were presented by the animation model of Kuosheng NPP.
