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研究生: 許修維
Hsu, Hsiu-Wei
論文名稱: 風險告知安全分析方法論之研究與應用-核三廠SBLOCA重要安全事故序列分析
Research and Application of Risk-informed Safety Methodology – Major Safety Event Sequence Analysis of Maanshan Nuclear Power Plant SBLOCA
指導教授: 白寶實
Pei, Bau-Shei
梁國興
Liang, Kuo-Shing
口試委員: 苑穎瑞
Yuann, Yng-Ruey
曾永信
Tseng, Yung-Shin
學位類別: 碩士
Master
系所名稱: 原子科學院 - 核子工程與科學研究所
Nuclear Engineering and Science
論文出版年: 2018
畢業學年度: 106
語文別: 中文
論文頁數: 40
中文關鍵詞: 馬鞍山電廠風險告知安全餘裕特性分析爐心冷卻再回復小破口爐心冷卻水流失
外文關鍵詞: MaanshanNPP, RISMC, CoreCoolingRecovery, SBLOCA
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  • 過去的核能電廠安全對於分析超過設計基準事件,一般使用PSA方法計算事故序列發生的CDF(core damage frequency),然而其以大量假設條件及成功準則的評估並未充分考量參數的不確定性。RISMC(Risk-Inform Safety Margin Characterization)方法在分析事故序列時,加入其隨機不確定性的特質,將產生別於傳統方法的結果。在同時考慮事故嚴重性與發生頻率下,本文以台電核三廠廠內事件量化分析報告中事故序列CDF大於1.0E-07/y前十名中的第三名(前一二名分別是喪失4.16 kV緊要匯流排A串肇始事件與蒸汽產生器管束破裂) ─ 小破口爐心冷卻水流失(SBLOCA)序列S(2)S20為研究案例,驗證不同方法論的差異。在此事故序列中,儘管於台電核三廠人為可靠度分析報告中已充分估計人因條件失效概率,但在考量參數的隨機不確定性後,實際允許的救援時間將受到極大的影響,進而可能使失效概率有所變化,而非報告中假設固定的時間。本文希望能透過熱工水流程式RELAP5-3D來模擬納入電廠條件與人因參數不確定性的SBLOCA事故序列,並使用統計方法擬合密度機率函數以評估事故發生下運轉員進行「爐心冷卻再回復」的成功概率,進而與過去的CDF數據比較。


    For analysis of Beyond Design Basis Event, PSA methods would be initiated to determine event sequences’ frequency of core damage. However, its estimation utilizing large numbers of conditional assumptions and criteria don’t have sufficient consideration of parameters uncertainty. RISMC method which addresses aleatory uncertainty would generate different result compared with traditional way. In light of both of sequences’ damage and frequency, this research uses Small Break Loss of Coolant Accident event sequence S(2)S20, 3rd of top ten internal initiating event sequences with highest core damage frequency over 1.0E-7/year ranked in Probabilistic Risk Assessment Maanshan Nuclear Power Station Final Report, as example (which 1st and 2nd are Loss of Safety 4.16kV Bus A-PB-S02 and Break of Steam Generator Tube respectively) to evaluate degree of difference between two methods. Although it already has a comprehensive estimation of Human Reliability Conditional Exceedance Probability in Maanshan Nuclear Power Plant Human Reliability Report, the actual operation time would be extremely affected if taking aleatory uncertainty as consideration. This research is expected to use RELAP5-3D to simulate SBLOCA event sequence with both plant operation factor and human factor parameters uncertainty. Then utilize statistical methods to approach probability distribution function, calculating operation success rate in step of Core Cooling Recovery. The result would be compared with past data in safety report.

    摘要 i ABSTRACT ii 致謝 iii 目錄 iv 表目錄 vi 圖目錄 vii 第一章 背景 1 1.1 安全分析方法論簡介 1 1.2 核三廠簡介 3 1.3 RELAP5-3D 4 1.3.1 核三廠輸入檔 4 1.3.2 爐心的模擬 5 1.3.3 二次緊急側飼水系統 5 第二章 核三廠小破口冷水流失事故 7 2.1 小破口冷卻水流失事故序列 7 2.2 人為可靠度分析 9 2.2.1 CBDTM之決策樹 10 2.2.2 HCR允許時間內未能完成的機率 11 2.2.3 THERP分析方法 12 第三章 實驗方法與流程 15 3.1 不確定性參數設定與取樣 15 3.2 數據分析與統整 21 3.2.1 常態分布適配度檢定 24 3.2.2 符合常態分布之情形 27 3.2.3 不符合常態分布之情形 29 3.2.4 限制抽樣對照組 34 第四章 結果與討論 39 第五章 參考文獻 40

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