| 核燃料包壳锆合金表面涂层研究进展 |
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| 引用本文： | 柏广海,陈志林,张晏玮,刘二伟,薛佳祥,余伟炜,王荣山,李锐,刘彤.核燃料包壳锆合金表面涂层研究进展[J].稀有金属材料与工程,2017,46(7):2035-2040. |
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| 作者姓名： | 柏广海 陈志林 张晏玮 刘二伟 薛佳祥 余伟炜 王荣山 李锐 刘彤 |
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| 作者单位： | 苏州热工研究院有限公司,苏州热工研究院有限公司,苏州热工研究院有限公司,苏州热工研究院有限公司,中广核研究院有限公司,苏州热工研究院有限公司,苏州热工研究院有限公司,中广核研究院有限公司,中广核研究院有限公司 |
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| 基金项目： | 苏州市2016产业技术创新专项(项目号：SYG201634),国家自然科学基金资助(项目号51271018； 51502322) |
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| 摘 要： | 锆合金表面涂层是提高核燃料包壳事故容错能力的重要途径之一。本文综述了锆合金表面涂层的研究进展,包括涂层种类、制备工艺、微观组织以及抗水蒸气氧化性能、耐腐蚀性能等,介绍了锆合金表面涂层种类选择的依据,探讨了涂层的制备工艺、微观组织与性能之间的关系,分析了当前研究中存在的若干问题及未来涂层的发展方向,为进一步促进核燃料包壳锆合金表面涂层的研究提供了有价值的参考。
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| 关 键 词： | 燃料包壳 事故容错 锆合金 涂层 水蒸气氧化 |
| 收稿时间： | 2016/8/29 0:00:00 |
| 修稿时间： | 2016/11/17 0:00:00 |
Research progress of coating on zirconium alloy for nuclear fuel cladding |
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| Bai Guanghai,Chen Zhilin,Zhang Yanwei,Liu Erwei,Xue Jiaxiang,Yu Weiwei,Wang Rongshan,Li Rui and Liu Tong.Research progress of coating on zirconium alloy for nuclear fuel cladding[J].Rare Metal Materials and Engineering,2017,46(7):2035-2040. |
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| Authors: | Bai Guanghai Chen Zhilin Zhang Yanwei Liu Erwei Xue Jiaxiang Yu Weiwei Wang Rongshan Li Rui and Liu Tong |
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| Affiliation: | Suzhou Nuclear Power Research Institute,Suzhou,Suzhou Nuclear Power Research Institute,Suzhou,Suzhou Nuclear Power Research Institute,Suzhou,Suzhou Nuclear Power Research Institute,Suzhou,China Nuclear Power Technology Research Institute,Shenzhen,Suzhou Nuclear Power Research Institute,Suzhou,Suzhou Nuclear Power Research Institute,Suzhou,China Nuclear Power Technology Research Institute,Shenzhen,China Nuclear Power Technology Research Institute,Shenzhen |
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| Abstract: | Coating on zirconium alloy is one of important way to improve the properties of fuel cladding under nuclear power plant accident. The research progress of coating on the surface of zirconium alloy are summarized in this article, which include types, preparation process, microstrutures, steam oxidation resistance properties and corrosion resistance properties. The selection basis of coating, and the relationship between preparation process, microstructure and steam oxidation resistance properties are discussed. Some problems in the present researches and development of coating are analyzed. The results can provide valuable references for promoting development of coating on nuclear fuel cladding. |
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| Keywords: | fuel cladding accident tolerant zirconium alloy coating steam oxidation |
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