本文使用PCTRAN核能電廠模擬軟體，針對台灣第二核能發電廠，進行電廠運轉過程中潛在性的暫態與事故分析，並且觀察這些事故發生後，於運轉中產生的訊號，同時對事故發生之機制進行探討。
因此，本文工作分為兩大階段，其一PCTRAN程式修正，其二為案例分析。程式修正部分，在PCTRAN原始程式之架構下，再以電廠參考資料為依據，對程式與基本參數進行修改，修改部分包含:水位高度、高壓噴灑系統與安全釋壓閥開關設定、汽機跳機與汽機停止閥關閉設定等。案例分析部份，使用修正之PCTRAN程式，對電廠設備失效時所引發的動作，以及運轉參數之結果作為比對依據，例如：反應器跳機、汽機跳機、飼水泵跳脫、安全釋壓閥開啟等動作，及反應器功率、主蒸氣流量、飼水流量及水位等參數變化。

ABSTRACT

This thesis used PCTRAN, a fast-running nuclear power plant simulation code, to analyze potential transients and accidents of the second nuclear power plant in Taiwan. The signals and mechanisms generated when accidents occur are also clarified.
Therefore, this work is mainly separated into two parts, which are the improvements of PCTRAN code and the case studies. In the first part, some improvements to the code were made referring to the KSNPP’s publications. The improvements include the water levels, HPCS setpoints, SRV setpoints, turbine trip logic, and turbine stop valve logic. In the second part, this modified code is used for case studies throughout this thesis. The case studies investigated the change of signals and parameters, such as scram, turbine trip, feedwater trip, SRV open, and parameters which are reactor power, mean steam flow, feedwater flow, and water levels.

[1]第二核能發電廠，" 沸水式核能電廠 "，第五版，中華民國九十二年十月
[2]第二核能發電廠，" 第二核能發電廠營運程序書－安全釋壓閥邏 輯功能試驗"，第十四版，中華民國九十二年十月
[3]Taiwan Power Company，" Final Safety Analysis Report " KuoSheng Nuclear Power Station，amendment NO.13，December 2003
[4]范光運，"利用電廠嚴重事故分析軟體MAAP4.0.4對PCTran KuoSheng程式的驗證 "，國立清華大學工程與系統科學系，中華民國九十二年九月