本研究主題為核電廠控制室適居性分析方法論之建立與應用，研究內容主要分為控制室輻射劑量及有毒物質濃度兩個部分，首先利用RADTRAD程式搭配圖形化介面程式SNAP，建立沸水式反應器(BWR)的國聖電廠(核二廠)之放射性核種遷移、移除與劑量評估模式，並將本研究室先前針對壓水式反應器(PWR)的馬鞍山電廠(核三廠)所建立之SNAP/RADTRAD模式加以精進，將兩模式應用於冷卻水流失(LOCA)設計基準事故(DBA)之圍阻體洩漏(release from the containment)案例的輻射劑量評估，同時也針對兩模式進行靈敏度分析，以了解調整之參數與分析結果的相關性。
有毒物質濃度分析的部分以HABIT及ALOHA，模擬國聖電廠與馬鞍山電廠二氧化碳儲存槽洩漏假想案例，分析控制室內二氧化碳濃度，並探討兩分析模式彼此間差異，了解各程式之優缺點，並將模式應用於核電廠周邊環境之濃度分析，確保人員生命安全，同時也針對兩程式進行靈敏度分析。
綜合各模式之分析結果發現，於分析的案例中，兩核電廠控制室之適居性皆得以保持，並於靈敏度分析中發現對分析結果影響較大的參數與較無關的參數。此分析方法論可提供核電廠與管制單位，針對控制室適居性分析的參考，本分析方法論也可依據分析對象與適用之情境選擇分析工具，以得到最佳分析結果，本分析方法論除了應用於國聖電廠與馬鞍山電廠，還可適用於其他核電廠，將來更可擴展至相關領域之劑量與濃度評估工作。

The overall objective of this study is the establishment and application of analysis methodology of control room habitability in nuclear power plant. The research is mainly divided into two parts: control room radiation dose and hazardous chemical concentration evaluation. First, the analysis model for Kuosheng Nuclear Power Plant was built by RADTRAD combined with the graphical interface SNAP. Besides, the SNAP/RADTRAD model built by the research colleagues for Maanshan Nuclear Power Plant was modified. The evaluation of the control room radiation dose of the case of release from the containment in Loss of Coolant Accident (LOCA) Design Basis Accident (DBA) was simulated by these two models. Meanwhile, the sensitivity analyses were performed to analyze the correlations between the parameters and the analysis results.
In the second part, the evaluations of carbon dioxide concentration in the control room in the hypothetical cases of the leakage from the carbon dioxide storage tank of Kuosheng Nuclear Power Plant or Maanshan Nuclear Power Plant were simulated by HABIT and ALOHA. The differences between these two analysis tools were investigated to understand the advantages and disadvantages of each code. Furthermore, the evaluations of carbon dioxide concentration of the surrounding environment of nuclear power plants were simulated by these two codes to ensure the health of personnel.
Based on the results of the analysis, the habitability of the control rooms of the Kuosheng Nuclear Power Plant and Maanshan Nuclear Power Plant was maintained. In the meanwhile, parameters that affect the results obviously are shown in the sensitivity analysis. This analysis methodology could be a reference for analysis of control room habitability and applied to other nuclear power plants as well as fields related to the evaluations of radiation dose and hazardous chemical concentration in the future.

摘要 i
ABSTRACT iii
誌謝 v
目錄 vi
表目錄 viii
圖目錄 xi
符號縮寫表 xiii
第一章 緒論 1
1.1　研究動機與目的 1
1.2　分析方法論流程與論文架構 2
第二章 文獻回顧 4
第三章 程式與電廠介紹 7
3.1　 SNAP/RADTRAD程式介紹 7
3.2　 HABIT程式介紹 10
3.3　 ALOHA程式介紹 11
3.4　 國聖電廠(核二廠)介紹 13
3.5　 馬鞍山電廠(核三廠)介紹 14
第四章 圍阻體洩漏假想事故模擬與靈敏度分析 18
4.1　國聖電廠圍阻體洩漏假想事故介紹 18
4.2　國聖電廠圍阻體洩漏假想事故SNAP/RADTRAD模式介紹 19
4.3　國聖電廠圍阻體洩漏假想事故SNAP/RADTRAD模擬結果與結論 27
4.4　馬鞍山電廠圍阻體洩漏假想事故介紹 32
4.5　馬鞍山電廠圍阻體洩漏假想事故SNAP/RADTRAD模式介紹 32
4.6　馬鞍山電廠圍阻體洩漏假想事故SNAP/RADTRAD模擬結果與結論 40
4.7　國聖電廠與馬鞍山電廠SNAP/RADTRAD模式靈敏度分析 46
第五章 二氧化碳儲存槽洩漏假想事故模擬與靈敏度分析 57
5.1　利用HABIT模擬電廠二氧化碳儲存槽洩漏假想事故 61
5.1.1　國聖電廠二氧化碳儲存槽洩漏假想事故HABIT模式介紹 62
5.1.2　國聖電廠二氧化碳儲存槽洩漏假想事故HABIT模擬結果 64
5.1.3　馬鞍山電廠二氧化碳儲存槽洩漏假想事故HABIT模式介紹 66
5.1.4　馬鞍山電廠二氧化碳儲存槽洩漏假想事故HABIT模擬結果 68
5.2　利用ALOHA模擬電廠二氧化碳儲存槽洩漏假想事故 70
5.2.1　國聖電廠二氧化碳儲存槽洩漏假想事故ALOHA模式介紹 70
5.2.2　國聖電廠二氧化碳儲存槽洩漏假想事故ALOHA模擬結果 74
5.2.3　馬鞍山電廠二氧化碳儲存槽洩漏假想事故ALOHA模式介紹 79
5.2.4　馬鞍山電廠二氧化碳儲存槽洩漏假想事故ALOHA模擬結果 83
5.3　ALOHA與HABIT之結果比較與靈敏度分析 89
第六章 結論與建議 98
6.1　結論 98
6.2　建議 99
參考文獻 100

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