| Summary: | 碩士 === 國立清華大學 === 核子工程與科學研究所 === 100 === In this research, the management ability of Kuosheng Nuclear Power Plant’s safety system is evaluated in different conditions through simulates a situation similar to Fukushima accident. In addition, the decision-making strategies during such severe accident are provided in this research as well. The situation simulation is based on SBO and assumes that all the Emergency Core Cooling Systems fail. The Automatic Depressurization System is activated under the conditions of three different core water levels (1) TAF, (2) one-third of fuel rods uncovered, (3) BAF. When the core vessel reaches the low pressure of 0.779 MPa, the alternate water system is activated in sequent. All the analyses presuppose that the peak cladding temperature (PCT) does not exceed the limit of 1088.706K and the analysis results are evaluated in two considerations which are minimum alternate water flow and time scale. The analysis code used in this research, TRACE (TRAC/RELAP Advanced Computational Engine), is a modernized thermal-hydraulic code developed by the U.S NRC. It can perform best-estimate analyses of loss of coolant accidents (LOCAs), operational transients, and other accident scenarios in light-water reactors (LWRs). In order to enhance the reliability of Kuosheng TRACE model, 100% power load rejection start up test is chosen in this research and the verified results are in agreement on test data. Furthermore, the main analysis result of this research indicates that the alternate water system installed in Kuosheng NPP can cope with a similar accident as severe as Fukushima event. Besides, the design of sufficient flow rate extends the time needed for decision-making and effectively mitigates the urgency when such accident occurs.
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