摘 要

我國核三廠的Level 2 PSA作業，已於民國八十三年由核能研究所與台灣電力公司共同合作完成，當時由於尚未有嚴重事故處理指引（SAMG）的出現，因此核三廠的Level 2 PSA評估內容中並未包含SAMG的各項考量。本論文的研究目的之一即在於，將核三廠SAMG納入現有的Level 2 PSA中，並分析核三廠SAMG對於Level 2 PSA工作之各種衝擊與影響。再者，SAMG主要的發展哲學為盡可能的確保圍阻體在嚴重事故下的完整性，並全力防止放射性物質外釋至環境，在SAMG中提出了許多指引與建議，用來減緩嚴重事故對於圍阻體完整性的衝擊與控制放射性物質的外釋量。為此，本論文也將深入探討有關核三廠SAMG中，各項指引建議以及救援行動的適用性。
經由本論文的研究，有關SAMG對於核三廠Level 2 PSA的各項影響與改變均已被明確的提出；原本Level 2 PSA的人為失誤量化亦在本論文中作了適當的修正；在研究的過程中，對於SAMG所提及的核電廠嚴重事故下之救援策略，我們也以程式模擬以分析其適用性與正、負面效應。為評估SAMG納入Level 2 PSA後的影響，本論文也作了CSET的量化以驗證結果是否與我們預期的相同。除了評估SAMG對Level 2 PSA的影響外，本論文亦針對許多電廠可能發生的嚴重事故進行模擬分析，並得到許多寶貴的數據與結果，這些資料對於往後的核電廠安全評估將有相當的貢獻。

ABSTRACT

Probability Safety Assessment (PSA) is a holistic approach to estimate the reliability and safety of a nuclear power plant. PSA has been widely utilized by many nuclear utilities and its impact on the nuclear power plant (NPP) safety is very notable. Over the past few years, Severe Accident Management Guidance (SAMG), which delineates the mitigation actions of core meltdown accidents of NPP, is developed to support operators and staffs in the Technical Support Center (TSC) in dealing with those misfortunes. It can be expected that the implementation of SAMG will lower the risk of NPP operation. The execution of SAMG will lower the containment failure probability and will reduce the amount of radionuclides released to the environment during the accident. The mitigation actions in SAMG are not considered in the conventional Level-2 PSA analysis of PSA. In this study the mitigation actions of SAMG are incorporated into the Level-2 PSA of a Westinghouse three loops Pressurized Water Reactor (PWR). The plant analyzed is Maanshan Nuclear Power Plant of Taiwan Power Company. The purposes of the study are to assess the impact of SAMG on the risk of NPP and to identify the importance measure of these mitigation actions. This thesis summarizes the results of the study.

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