本研究主要針對核四廠所採用之進步型沸水式反應爐,應用由美國電力研究所(Electric Power Research Institute, EPRI)所發展的RETRAN-02 MOD5熱水流分析程式,進行評估模式的建立及負載棄載有/無旁通、汽機跳脫有/無旁通等暫態事件的模擬分析。分析的過程中並適度進行靈敏度分析(Sensitivity Analysis),以增對核四廠RETRAN-02 MOD5模式及系統特性的了解。本分析模式與初期安全分析報告書(Preliminary Safety Analysis Report, PSAR)分析結果比較顯示仍有部分的差異,往後將朝汽機蒸汽旁通系統的模擬方式作進一步的改良,期能與PSAR旁通系統的設計相當以獲得更準確的計算結果。而本研究證明了當核四廠發生負載棄載及汽機跳脫有旁通事件時,以核四廠進步型沸水式反應爐機組之汽機旁通110%蒸汽流量、旁通閥快速開啟之設計確能有效地避免反應爐急停。
The purpose of this study is to evaluate the development of model and the event simulations of the load rejection with and without bypass and the turbine trip with and without bypass for the Lungmen Nuclear Power Plant (an advanced boiling water reactor, ABWR), using the RETRAN-02 MOD 5 thermal-hydraulic analytical methodology developed by the Electric Power Research Institute (EPRI). In addition, sensitivity analyses were performed to enhance the understanding of the modeling and system features of the RETRAN-02 MOD 5 methodology. Subsequently, comparisons of the results obtained in this study with those obtained from the PSAR (Preliminary Safety Analysis Report) of the Lungmen Nuclear Power Plant were made and differences between the two studies were noted. In the future, improvement on the modeling of the steam bypass system will be carried out. It is expected that by doing so, the design of the bypass system will be compatible with that of the PSAR so that a better agreement can be obtained from future studies. The result obtained from this study indicated that the design of a prompt opening of the bypass valve can effectively avoid the scram of the reactor for the Lungmen Nuclear Power Plant with a turbine bypass capacity of 110% steam flow rate during the events of load rejection with bypass and turbine trip with bypass.