摘 要
PCTRAN ABWR是由台電公司向美國 MST 團隊所引進的一套快速分析程式，它的功能是利用個人電腦的優越能力，來模擬核電廠的各項暫態及各種事故的評估。本論文研究的對象為核四廠版本的PCTRAN ABWR程式與 PSAR事故分析之結果與驗證，希望藉由分析 PSAR所提及的各項案例結果了解並驗証 PCTRAN ABWR的分析能力及其可靠度。
我們將對PSAR第十五章裡，所提及的案例做模擬與研究。本論文首先介紹 PCTRAN ABWR的重要功能與特色，之後我們會列出PSAR所提及的核電廠參數，最後依據 PSAR 的案例分析，經由PCTRAN ABWR分析模擬並加以探討。
經由比對與驗證，我們發現PCTRAN ABWR分析結果與PSAR之結果有一定的相似度，但也發現一些現象值得我們加以探討。如不能讓兩台飼水泵真正的失效、在程式中缺乏真實電廠的啟動與取消的訊號邏輯、同時設定汽機控制閥與汽機氣體旁通閥關閉時有困難、中子通率有偏低的情況等問題。

ABSTRACT
PCTran ABWR is a fast-running simulation code for Lungmen nuclear power plant. The code was developed by Micro-Simulation Technology and implemented by Taiwan Power Company (TPC). PCTran can be installed in a PC under Windows operating system and has excellent ability to simulate transients and accidents in a nuclear power plant.
In the thesis, we tried to use PCTran ABWR to simulate and compared cases chosen from Preliminary Safety Analysis Report (PSAR). The simulated cases are mainly selected from the chapter 15 in PSAR.
This thesis first introduced the important function and features of PCTran. And then, the significant parameters accounted in PSAR are listed. Finally, according to the cases analyzed in PSAR, we simulated these cases by using PCTran ABWR code and compared the results between PSAR and PCTran. The simulating ability and reliability of PCTran ABWR can be evaluated after the comparison
Through the comparisons between PCTran ABWR and PSAR, we noticed that all results are quite similar. But we need further research for some transient simulation results. For example, we found that we could not fail all feedwater pumps during the simulation. Some logics for signal triggering are not the same as in PSAR. There is also some difficulties manipulating turbine control valve and bypass valve failure at the same time. The neutron flux responses are not quite sensitive as it should be.

參考文獻

[1] Po, L. C., “PCTRAN ABWR Personal Computer Transient Analyzer”，Micro-Simulation Technology, 2002
[2] 儀控軟體風險分析發展與應用，行政院原子能委員會委託研究計畫研究報告，中華民國九十三年十二月十日
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[4] 「台灣電力公司核能四廠ABWR訓練教材」，台灣電力公司第四核能電廠，中華民國九十二年
[5] 陳玉柱，核電廠事故分析PCTRAN之引進與應用，國立清華大學工科系碩士論文，中華民國九十年六月五日