- 學位論文
核四廠RELAP5/MOD3輸入數據建立與暫態事故分析
Transient Analyses of Advanced Boiling Water Reactor of Lungmen Nuclear Power Station using RELAP5/MOD3
摘要
本研究是針對台灣電力公司核四廠 – 進步沸水式核能電廠，以RELAP5/MOD3 熱水流分析程式作部分核四廠終期安全分析報告（Final Safety Analysis Report, FSAR）暫態事故分析。 台灣電力公司核四廠，採用兩部美國奇異公司所發展之135萬千瓦之進步型沸水式反應器，本研究建立核四廠RELAP5/MOD3輸入數據，包含了反應爐壓力槽系統（RPV）與電廠平衡系統（BOP）；詳細模擬汽機、熱交換器、再加熱器與水泵等機制，但並未建立中子計算所需之參數。建立之核四廠RELAP5/MOD3輸入數據已可完成穩態計算。 模擬之暫態系參考包含：爐內水泵跳脫，主蒸汽隔離閥關閉。模擬結果與核四廠FSAR報告比對，顯示因為輸入數據中尚未建立控制系統，因此暫態模擬的結果並不如預期。
並列摘要
In this study, a reactor system thermohydraulic system analysis code, RELAP5/MOD3 is used to analyzed selected transients in the Final safety analysis report (FSAR) of Lungmen Nuclear Power Stations (NPS).The plant employs two general electric designed Advanced Boiling Water Reactor (ABWR) with rated power of 1350MWe. The Lungmen input deck of RELAP5/MOD3, models reactor pressure vessel (RPV) and banlance of plant (BOP), which includes major components such as turbines, heat ecxhangers , reheaters, and pumps. The input deck has been successfully initialize to a steady state condition. The internal pump trip and main steam line isolation valves closures transients in FSAR of Lungmen NPS are simulated. The results are compared with the data in FSAR. The comparsion of the simulated results with the results shown in FSAR are not satisfactory due to lack of modeling of the control system in the input deck.