2004-01-012024-05-18https://scholars.lib.ntu.edu.tw/handle/123456789/703729摘要：過去顯少文獻提及核電廠飼水加熱器之老化問題及其相關之研究，但在美國Point Beach核電廠飼水加熱器於1999年因蒸汽流動加速腐蝕造成破裂後，美國核管會及美國電力研究院才參與相關之老化、劣化研究。而國內部份，原能會亦於2000年起，要求三座核能電廠參照美國核管會規定，進行飼水加熱器之檢查與監測工作。事實上，由他們三年來之超音波檢測結果得知，國內電廠飼水加熱器殼側之薄化情形遠遠超過原來之預估值，而面臨立即修補、進行監測及提出改善方案等問題。本研究之目的即在協助國內電廠及管制單位提出各項可靠度評估與管理技術，並探討他們的可行性，進而將其應用於飼水加熱器之老化評估與管理技術上，同時在風險基之考量下，施予適當之維護管理方案。 <br> Abstract: The aging of feedwater heaters (FWH) in nuclear power plants has not been a problem until the occurrence of rupture of the feedwater heater at Point Beach Nuclear Power Plant in the USA in 1999. It was later diagnosed to be caused by flow-accelerated corrosion. Since then, the USNRC and EPRI have started researches related to the aging and life extension of FWH. Domestically, starting from 2000, AEC has requested each nuclear power plant to inspect and monitor its FWH in accordance with NRC’s proposition. In fact, it has been found through ultrasonic inspection that thinning problem at the shell side of FWH of domestic nuclear power plants is serious than it was originally expected. Thus, each power plant faces problems of inspection, monitor, proposition of improvement and/or fixing its FWH system. In the proposed project, the aging and life extension problems of FWH will generally be studied. Special emphases will be put on the structural integrity analysis, reliability assessment, and risk-informed inspection and management of FWH. Appropriate maintenance and management strategies for the FWH in domestic power plant will be proposed after the study.飼水加熱器流動加速腐蝕老化評估Feedwater HeaterFlow-Accelerated CorrosionAging Assessment