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題名 | 核一廠LERF暨AFPCS分析更新研究=Study of LERF and AFPCS Update Analysis for Chin-Shan Nuclear Power Plant in Taiwan |
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作者 | 周源卿; 羅武斌; 李政峰; 李政峰; Chou, Yuan-ching; Lo, Wu-pin; Li, Jheng-fong; Li, Jheng-fong; |
期刊 | 龍華科技大學學報 |
出版日期 | 20130600 |
卷期 | 33 2013.06[民102.06] |
頁次 | 頁17-27 |
分類號 | 449.7 |
語文 | chi |
關鍵詞 | 故障樹分析; LERF; PRA; AFPCS; Fault tree analyses; |
中文摘要 | 美國核管會(NRC)將CDF 與LERF 作為核能電廠風險評估之監管指標。在NUREG/CR-6595 中應用PRA Level-1 之結果,搭配標準化之PRA Level-2 圍阻體事件樹(CET),提供一個速捷的LERF 評估方法。我國核一廠參照上述方法所得之LERF 結果反映圍阻體系統對減緩事故後果的貢獻。但核一廠現有之LERF 評估並未考量圍阻體物理現象事件樹(CPET)。本論文為評估圍阻體物理現象對LERF 之影響,將核一廠CPET分析結果納入現有之LERF 分析中,以評估其間之差異。研究結果顯示,導入CPET 後,廠內事件之LERF 降低了74.36%;廠外之地震事件與颱風事件分別減少26.01%及78.47%;廠內及廠外事件之總LERF 減量達38.62%。由結果可知導入CPET 後較能反映核一廠之實際狀況。另本論文對核一廠的用過燃料池冷卻系統進行失效率的評估,並依改善方案假設了三組設計案。 |
英文摘要 | U.S. NRC (Nuclear Regulatory Commission) adopts LERF (Large Early Release Frequency) to estimate the probability of early fatalities due to radiological release in nuclear power plant accident, and also made CDF (Core Damage Frequency) and LERF as oversight indicators for the nuclear power plant risk. NUREG/CR-6595 provided a simple LERF assessment method. It applies the PRA Level-1 results with a standard CET to conduct the LERF assessment. Chin-shan Nuclear Power Plant adopted similar approach but using CSET (Containment System Event Tree) to reflect the effects of containment safety systems on LERF. However, the LERF assessment for Chin-shan Nuclear Power Plant did not take CPET (Containment Phenomenological Event Tree) into consideration. To make the effects of containment physical phenomena on LERF more clear, this study integrates CPET into the existing LERF assessment for Chin-shan Nuclear Power Plant, and compared the results with the existing analysis results. The results of comparisons show that, after integrating the effects of CPET, the new LERFs reduced by 74.36 %, 26.01% and 78.47% for internal, typhoons, and earthquake initiated events respectively. And the total LERF is reduced by 38.62%. It is clear that the original LERF analysis is more conservative, and the LERF obtained in this study can further reflect the effects of containment physical phenomena on large early release accidents. This study also investigates the effects of the “specific strengthening measure and improving program” on Chin-shan CPET. The program was implemented by Taiwan Power Company after Japanese Fukushima accidents. In this program, although the improvement of spent fuel pool cooling capability did not affect CPET very much, but it plays an important role in the improvement activities after the Fukushima nuclear disaster. For this concern, three strengthened AFPCS (Advance Fuel Pool Cooling System) designs are analyzed by using Fault Tree technology in this study. The relative cost, construction complexity, and failure probabilities of the three designs are compared and can be used as reference information for relevant decision making. |
本系統之摘要資訊系依該期刊論文摘要之資訊為主。