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研究生: 何泉漢
Ho, Chuan Han
論文名稱: 304L不銹鋼和316L不銹鋼於模擬沸水式反應器起動狀態之水化學環境中的應力腐蝕龜裂行為研究
Stress Corrosion Cracking of Type 304L Stainless Steels and Type 316L Stainless Steels in Simulated Boiling Water Reactor Water Chemistry Environments under Start-up Conditions
指導教授: 葉宗洸
Yeh, Tsung-Kuang
口試委員: 黃俊源
Huang, Jiunn-Yuan
馮克林
Fong, Clinton
王美雅
Wang, Mei-Ya
學位類別: 碩士
Master
系所名稱: 原子科學院 - 核子工程與科學研究所
Nuclear Engineering and Science
論文出版年: 2018
畢業學年度: 106
語文別: 中文
論文頁數: 152
中文關鍵詞: 應力腐蝕龜裂慢應變速率拉伸試驗沸水式反應器加氫水化學
外文關鍵詞: BWRs, SCC, SSRT, HWC
相關次數: 點閱:2下載:0
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  • 04L不銹鋼和316L不銹鋼對於應力腐蝕龜裂(Stress Corrosion Cracking, SCC)有較高的敏感性,為了確保沸水式反應器(Boiling Water Reactor, BWR)結構組件的完整性,目前已有相當多的電廠採用了加氫水化學(Hydrogen Water Chemistry, HWC)技術。利用降低腐蝕電位(Electrochemical Corrosion Potential, ECP)來達到腐蝕抑制的效果。然而由於技術運轉規範的限制,台灣現行的核電廠設計在功率達到90%後才啟動加氫系統,考量到反應爐起動時特殊的水化學狀態,在此運轉條件下材料的腐蝕狀況值得加以重視和研究。
    本研究採用慢應變速率拉伸實驗(Slow Strain Rate Test, SSRT)探討兩種低碳不鏽鋼在不同熱處理後,於一般水環境 (Normal Water Chemistry, NWC) 以及加氫水化學等兩種水化學環境下的應力腐蝕龜裂行為。試棒為棒狀圓柱,主要實驗溫度為288℃、250oC和200oC,拉伸速率為3.0 × 10-7 /s。接著以掃描式電子顯微鏡(Scanning Electron Microscopy, SEM)分析斷裂面型態以及表面樣貌。結果顯示316L不銹鋼相較於304L不銹鋼有較好的抗沿晶腐蝕能力。同時,在一般水化學環境下,對兩種不銹鋼而言較低的溫度都有著較低的應力腐蝕龜裂敏感性,其中316L在150oC下和304L在200oC下都無應力腐蝕龜裂出現,然而在250oC和288oC的結果都有著傾向多重裂縫起始的破裂形貌,呈現了較嚴重的應力腐蝕龜裂特徵。而加氫水化學的採用對於敏化316L抵抗應力腐蝕龜裂劣化有良好的效果,然而對於304L其優化效果卻不如預期。推論由於加氫水化學環境上和材料本身以及熱處理的差異造成不同的結果。其中加氫水化學中的氫/氧莫耳比、不銹鋼中的鉬和鎳含量造成了304L不銹鋼對於穿晶應力腐蝕龜裂可能有著較高的敏感性。


    Hydrogen water chemistry (HWC) was proposed and widely adopted in BWRs worldwide to mitigate the problem of SCC. However, the hydrogen injection can only be applied during normal plant operation due to some limits inherent in the original design. The pressure and temperature gradient during plant start-up could cause the tensile stress conditions. Regarding the water environment, the above factors may contribute to the initiation of SCC.
    In this study, we compared the SCC behavior between two type of stainless steel with different heat treatments at various temperature in the NWC and HWC during start-up. The SCC behavior and high temperature tensile properties were investigated by performing slow strain rate tensile (SSRT) tests at a constant strain rate of 3.0 × 10-7/s mainly at 200°C, 250°C and 288°C. After SSRT tests, scanning electron microscopy (SEM) was conducted to characterise the fractured surface. Basically, these two materials in the NWC test conditions showed lower SCC susceptibility with the lower testing temperature. Specimens tested under 250oC, however, showed higher tendency toward multiple cracks initiations. On the other hand, the performance of sensitized 316L in the aspects of tensile properties and fractography was substantially improved after introducing the HWC. Nevertheless, the unexpected performances were found on sensitized 304L after injecting hydrogen into the system. The slight differences between materials, heat treatment and water chemistry in the testing conditions were considered as the mian causes of these results.

    摘要 i Abstract ii 誌謝 iii 目錄 iv 表目錄 vii 圖目錄 viii 第一章 前言 1 1.1 研究動機-沸水式反應器組件完整性的問題 1 1.1.1 沸水式反應器組件材料的使用 1 1.1.2 沸水式反應器組件材料面臨的挑戰 3 1.2 研究目標 5 第二章 文獻回顧 6 2.1 應力腐蝕龜裂 6 2.1.1 304L不銹鋼和316L不銹鋼 6 2.1.2 應力腐蝕龜裂的肇因 7 2.1.3 應力腐蝕龜裂的現象描述 9 2.1.4 核電廠中的應力腐蝕龜裂因素 11 2.1.5 沃斯田鐵系不銹鋼於高溫純水中之氧化層結構 18 2.1.6 應力腐蝕龜裂的機制 27 2.1.7 沃斯田鐵系不銹鋼的應力腐蝕龜裂破壞型態 42 2.2 應力腐蝕龜裂的防治技術-加氫水化學 49 2.2.1 加氫水化學的理論基礎 49 2.2.2 反應器起動時水化學評估 51 2.2.3 加氫水化學的實際效益 54 2.2.4 加氫水化學面臨的挑戰 61 2.2.5 氫對沃斯田鐵系不銹鋼在高溫純水中的影響 63 2.3 評估應力腐蝕龜裂的方法 67 2.3.1 慢應變速率拉伸試驗 67 2.3.2 溫度對應力腐蝕龜裂的影響 71 2.3.3 拉伸速率對應力腐蝕龜裂的影響 79 2.3.4 應力腐蝕龜裂破裂形貌之轉變 82 第三章 實驗設備及步驟 85 3.1 實驗設計及方法 85 3.2 試片前處理 88 3.3 慢應變速率拉伸試驗 89 3.4 沿晶腐蝕敏感性測試 92 3.4.1 草酸測試 92 3.4.2 雙環電化學再活化法 93 第四章 結果與討論 96 4.1 304L不銹鋼和316L不銹鋼的沿晶腐蝕敏感性 96 4.2 起動狀態下一般水化學環境中的慢應變速率拉伸結果 99 4.2.1 應力-應變曲線結果 99 4.2.2 破裂面SEM分析 103 4.3 起動狀態下加氫水化學環境中的慢應變速率拉伸結果 130 第五章 結論 153 第六章 未來工作 155 參考文獻 156

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