日本福島核子事故顯示出電廠在面對超過設計基準事故時緊急替代設備與人員訓練的不足。面對類福島事故，除了強化電廠設施外，台灣電力公司提出斷然處置程序之目的是在事故發生初期便立即進行降壓操作，若廠內正規注水系統不可用，則同時利用替代注水設備，以確保核燃料被水覆蓋。
本研究使用TRACE模擬與分析馬鞍山電廠(三迴路壓水式核電廠)發生電廠全黑事故與破口喪失冷卻水事故，探討斷然處置程序在面對複合式災變發生時的事故緩和能力，並利用FRAPTRAN程式對核燃料行為進行分析，確保核燃料是否符合以下規範：一、護套最高溫度需在1477K以下，二、護套氧化層厚度不可超過護套厚度之17%，三、護套應變不可超過0.01。
本研究分為三大部分，第一部分為先模擬馬鞍山電廠假想電廠全黑事故五種處置案例，並分析核燃料行為。第二部分為模擬電廠假設發生大破口喪失冷卻水與小破口喪失冷卻水事故，並對核燃料行為分析。第三部分為模擬電廠假設發生電廠全黑事故且同時發生破口喪失冷卻水事故，並對破口大小進行靈敏度分析與核燃料行為分析。
經過分析後發現，在本研究假設前提下，模擬結果顯示斷然處置措施能夠有效地應對電廠全黑，或是發生破口喪失冷卻水事故時，皆能確保燃料安全。

Fukushima Daiichi Nuclear Power Plant (NPP) occurred the disaster, which was caused by the earthquake and tsunami. To handle the Fukushima-like conditions, Taiwan Power Company proposed the Ultimate Response Guideline (URG) to ensure the NPP safety. The purpose of this mitigation strategy is to keep the fuels under water. The current criteria are listed as follows: (1) The Peak Cladding Temperature (PCT) is below 1088 K (1500°F) for Station-Blackout (SBO) and below 1477 K (2200°F) for loss of coolant accident (LOCA). (2) The maximum thickness of the cladding oxidation shall not exceed 17% of the cladding thickness. (3) The cladding strain shall not exceed 0.01.
In this study, the analysis of TRACE was performed for a Maanshan Nuclear Power Plant severe accident (LOCA and SBO). The Fuel rod behavior analysis by using FRAPTRAN code was also performed. In addition, three parts of simulation are presented in this study. First part is five cases analysis for SBO. Second part is small and large break LOCA analysis. Last part is five different break size cases analysis for LOCA+SBO.
According to the analysis results, it shows that the URG can effectively cope with the SBO. The URG can also cope with the LOCA and the fuel rod safety can be maintained during the SBO or LOCA.

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