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研究生: 葉璟賢
Yeh, Chin-Hsien
論文名稱: 核電廠除役過渡階段緊要區域之鑑定與評估
Identification of Vital Areas During Nuclear Power Plants Transitional Stage of Decommissioning
指導教授: 馮玉明
Ferng, Yuh-Ming
王仲容
Wang, Jong-Rong
口試委員: 曾永信
Tseng, Yung-Shin
楊榮華
Yang, Jung-Hua
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: 69
中文關鍵詞: 緊要區鑑定風險評估除役
外文關鍵詞: PRA, Vital area, Decommissioning
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  • 核電廠在除役階段時爐心之用過燃料棒將會退至用過燃料池中存放,而原本電廠的風險將會從爐心轉移至用過燃料池中。透過除役期間的用過燃料池安全度評估以及Sandia National Laboratories, Vital Area Identification for U.S. Nuclear Regulatory Commission與IAEA Technical Guidance Identification of Vital Areasat Nuclear Facilities給各國對於緊要區域鑑定之建議,制定緊要區域鑑定方法論,分析於除役階段可能遭受的肇始事件、廠內外事件,找出最有可能發生事故的區域或是發生事故最為嚴重的區域,訂定出一套流程,以利國內核電廠進行緊要區的鑑定並且劃分更為精準,得以更有效率的保護重要區域。


    At the stage of decommissioning in Taiwan, because of the full spent fuel pool, the dome of reactor will open and the spent fuel rods will stay in the reactor core for a long time. In this stage, the risk of power plant will different form decommissioning stage or operating stage. The situation of transitional stage of decommissioning is like outage stage and decommissioning stage. This study will compare the probabilistic risk analysis of both stage, outage and decommissioning stage, then select useful information by using qualitative analysis and international standards, and then identify the vital areas during transitional stage of decommissioning by Saphire. The probabilistic risk analysis of transitional stage is different form outage stage and decommissioning stage. And this study using vital area identification, it can point out the more important area and the area risk, is different from traditional probabilistic risk analysis, it points out the individual risk of every equipment. Through the vital area identification process, the power plant can protect the important areas during transitional stage more efficiently and precisely.

    目錄 摘要 i Abstract ii 致謝 iii 目錄 iv 表目錄 vi 圖目錄 viii 第一章 緒論 1 1.1研究背景 1 1.2研究目的 2 第二章 文獻回顧 3 第三章 SAPHIRE風險評估分析程式 13 3.1 程式簡介 13 3.2 PRA理論方程式 13 第四章 緊要區域PRA方法論 16 第五章 核一廠緊要區分析 21 5.1廠內事件分析 21 5.1.1冷卻水流失 22 5.1.2喪失燃料池冷卻 23 5.1.3喪失廠外電源 24 5.1.4廠內水災 25 5.1.5廠內火災 26 5.1.6非預期臨界 27 5.1.7重物掉落 28 5.2廠外事件分析 28 5.3緊要區分析 33 第六章 室內乾式貯存護箱分析 39 6.1肇始事件分析 39 6.2事件樹分析 52 6.3故障樹分析 55 第七章 結果與討論 62 參考文獻 64 附錄 68 SAPHIRE使用介紹 68

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