吴亚文,贺秀杰,张继龙,马显锋,施惠基.锆合金表面CrAl基耐高温涂层及氧化行为研究[J].表面技术,2018,47(9):34-41.
WU Ya-wen,HE Xiu-jie,ZHANG Ji-long,MA Xian-feng,SHI Hui-ji.CrAl-based High-temperature Coatings on Zirconium Alloy and Oxidation Behavior[J].Surface Technology,2018,47(9):34-41 |
| 锆合金表面CrAl基耐高温涂层及氧化行为研究 |
| CrAl-based High-temperature Coatings on Zirconium Alloy and Oxidation Behavior |
| 投稿时间：2018-02-01 修订日期：2018-09-20 |
| DOI：10.16490/j.cnki.issn.1001-3660.2018.09.005 |
| 中文关键词: 核电事故容错燃料 涂层 CrAlN CrTiAlN 耐高温氧化 |
| 英文关键词:nuclear ATF coatings CrAlN CrTiAlN high-temperature oxidation resistance |
| 基金项目:广东省教育厅青年创新人才项目（2016KQNCX005）；中山大学“百人计划”科研启动资助 |
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| Author | Institution |
| WU Ya-wen | 1.Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, China;2.School of Physics, Sun Yat-sen University, Guangzhou 510275, China |
| HE Xiu-jie | 1.Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, China |
| ZHANG Ji-long | 3.School of Physics, Claude Bernard Lyon 1 University, Lyon 69100, France |
| MA Xian-feng | 1.Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University, Zhuhai 519082, China |
| SHI Hui-ji | 4.AML, School of Aerospace, Tsinghua University, Beijing 100084, China |
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| 中文摘要: |
| 目的 了解锆合金和涂层的高温氧化行为，通过表面涂层提升锆合金的耐高温氧化性能。方法 采用多弧离子镀技术在锆合金基体上制备了CrAlN、CrTiAlN涂层，模拟反应堆失水（LOCA）事故时的高温氧化行为，在360~1160 ℃下进行1 h氧化测试，对原始锆合金和带涂层样品的氧化增重行为进行了研究。通过X射线衍射和扫描电子显微镜对氧化前后样品的物相结构和形貌进行系统表征分析。结果 锆合金在760 ℃及以下形成深色的混合型锆氧化膜，在860 ℃以上呈现龟裂和局部剥落。两种涂层氧化时，通过形成致密的Cr2O3和Al2O3混合氧化层，显著降低了氧化增重。CrAlN涂层在760 ℃时具有较好的抗氧化性，1060 ℃时开裂而失去保护作用。CrTiAlN涂层在860 ℃时能保护基体不受氧化，1060 ℃时局部开裂，基体开始出现氧化层。结论 利用多弧离子镀技术制备的锆合金表面CrAlN和CrTiAlN涂层，在模拟反应堆LOCA事故下具有良好的耐高温氧化性，显示出这两种涂层有潜力发展成为核用事故容错燃料（ATF）包壳涂层。 |
| 英文摘要: |
| The work aims to understand high-temperature oxidation behavior of zircaloy and coatings, and to improve high temperature oxidation resistance of zircaloy. CrAlN and CrTiAlN coatings were deposited on zirconium alloys by adopting multi-arc ion plating technique, high-temperature oxidation behavior in loss of coolant accident (LOCA) in nuclear power plant was simulated, oxidation tests were conducted for 1h at 360~1160 ℃ to study oxidation weight gain behavior of original zirconium alloy and coated samples. X-ray diffractometer and scanning electron microscope were used to systematically characterize and analyze phase structure and morphology of the samples before and after oxidation. Fuscous mixed zirconium oxide film was formed on the surface of zirconium alloy at the temperature below 760 ℃, and the film presented cracking and local spalling at the temperature over 860 ℃. Both coatings significantly decreased the oxidation weight gain by forming a dense Cr2O3 and Al2O3 oxide layer. CrAlN coatings showed good oxidization resistance at 760 ℃ and lose protective effect at 1060 ℃; CrTiAlN coatings protected the substrate from oxidization at 860 ℃, oxide layer appeared on partially fractured substrate at 1060 ℃. CrAlN and CrTiAlN coatings can be potentially good candidates for accident tolerant fuel (ATF) cladding coatings since such coatings prepared by virtue of multi-arc ion plating technique exhibit excellent high-temperature oxidation resistance in simulated LOCA in reactors. |
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