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| 題 名 | Hastelloy N合金在熔鹽LiF-NaF-KF中的腐蝕行為=Corrosion Behavior of Hastelloy N in Molten LiF-NaF-KF |
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| 作 者 | 李宥瑄; 葉均蔚; 林樹均; 歐陽汎怡; | 書刊名 | 防蝕工程 |
| 卷 期 | 37:3 2023.09[民112.09] |
| 頁 次 | 頁26-32 |
| 分類號 | 440.25 |
| 關鍵詞 | 熔鹽式反應器; 高熵合金; 高溫腐蝕行為; Hastelloy N; Molten salt reactor; Nickel-based superalloy; High temperature corrosion behavior; |
| 語 文 | 中文(Chinese) |
| DOI | 10.6376/JCCE.202309_37(3).0003 |
| 中文摘要 | 近年來,為了減少碳排放量,提升綠色能源的發展逐漸受到重視,而核能發電也是相當重要的一 環。於核能發電的發展中,根據不同冷卻劑及中子運作形式,設計一系列第四代核能反應器。研究針對 其中熔鹽式反應器 (Molten salt Reactor, MSR),其爐心出口溫度約在 600 至 800 ℃。因材料處於高溫熔 鹽環境時,抗氧化層的溶解會導致嚴重腐蝕的發生,因此以高溫抗腐蝕為目標,研究並觀察 600 ℃時持 溫 100 小時對鎳基合金 Hastelloy N 的腐蝕行為。研究結果顯示,經高溫 FLiNaK 熔鹽腐蝕後,合金的腐 蝕嚴重,其重量損失百分比為 40.9 %,且腐蝕影響區厚度約 301.1 m,而此腐蝕影響區的主要耗乏元素 為 Cr 及微量的 Mo 元素,推測是由於環境中水氣含量較多所導致。 |
| 英文摘要 | Recently, the development of green energy has gradually received attention to reduce carbon emission, and nuclear power has played an important role on it. In the development of nuclear power generation, a series of fourth-generation nuclear energy reactors are designed according to different coolants and neutron operation modes. The core outlet temperature of Molten Salt Reactor (MSR) is about 600 to 800 ℃. When the material is in a high-temperature molten salt environment, the dissolution of the anti-oxidation layer is expected to lead to severe corrosion. Thus, understanding the corrosion behavior of nickel-based Hastelloy-N alloy at 600 ℃ in molten salt environments is critical. The results of this study demonstrated that the mass loss percent of Hastelloy-N alloy was up to 40.9 % and the corrosion-affected zone was 301.1 m in depth. The main depleted elements in the corrosion-affected zone were Cr and small amount of Mo caused by the high content of water in the environment. |
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