脉冲激光熔覆制备ATF包壳Cr涂层的工艺与性能研究
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摘要
介绍了中广核研究院在事故容错燃料(ATF)包壳领域的最新成果,通过预置粉末式脉冲激光熔覆技术,在不同的功率下制备出不同厚度的锆包壳管Cr保护层;通过高温蒸汽氧化增重数据发现,采用半导体脉冲激光熔覆技术、脉冲激光功率50～60 W、螺距0.8～0.9 mm、角速度10°/s等参数条件下制备Cr涂层可以获得较好的抗高温氧化性能,证明保护的效果直接受涂层质量控制。通过SEM分析了涂层的显微结构,采用扩散机理解释了Cr涂层在1200℃下与锆合金基体相容性良好的原因。
This paper introduces the latest ATF cladding achievements of China General Nuclear Power Corporation(CGN). The Cr coating of Zircon with different thickness was prepared under different power by pulse laser cladding technique. The results obtained so far show that Cr coating can achieve good high temperature oxidation resistance which prepared using pulse laser cladding technology under the parameters such as pulse laser power for 50～60 W, pitch for 0.8～0.9 mm and angular velocity for 10 mm. The mechanism analysis shows that the Cr coating has good compatibility with the Zirconium alloy at 1200℃, and the protective effect of Cr coating is directly controlled by the coating quality.
This paper introduces the latest ATF cladding achievements of China General Nuclear Power Corporation(CGN). The Cr coating of Zircon with different thickness was prepared under different power by pulse laser cladding technique. The results obtained so far show that Cr coating can achieve good high temperature oxidation resistance which prepared using pulse laser cladding technology under the parameters such as pulse laser power for 50～60 W, pitch for 0.8～0.9 mm and angular velocity for 10 mm. The mechanism analysis shows that the Cr coating has good compatibility with the Zirconium alloy at 1200℃, and the protective effect of Cr coating is directly controlled by the coating quality.
引文
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[2]Ben-Belgacem M,Richet V,Terrani K A,et al.Thermomechanical analysis of LWR SiC/SiC composite cladding[J].Journal of Nuclear Materials,2014,447:125-142.
[3]Ece Alat,Arthur T.Motta,Robert J.Comstock,etc.Ceramic coating for corrosion(c3)resistance of nuclear fuel cladding[J].Surface&Coatings Technology,2015,281:133-143.
[4]Bo Cheng,Young-Jin Kim,Peter Chou.Improving accident tolerance of nuclear fuel with coated Mo-alloy Cladding[J].Nuclear Engineering Technology,2016,48:16-25.
[5]Hyun-Gil Kim,Jae-Ho Yang,Weon-Ju Kim,et al.Development status of accident-tolerant fuel for light water reactors in Korea[J].Nuclear Engineering Technology,2016,48:1-15.
[6]Ian Younker,Massimiliano Fratoni.Neutronic evaluation of coating and cladding materials for accident tolerant fuels[J].Progress in Nuclear Energy,2016,88:10-18.
[7]Jung-Hwan Park,Hyun-Gil Kim,Jeong-yong Park,et al.High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings[J].Surface&Coatings Technology,2015,280:256-259.
[8]Balart SN,Varela N,Tendler RH.51Cr diffusion inα-Zr single crystals[J].Journal of Nuclear Materials,1983,119:s59-66.
[9]Wen-Xing Xiang,Shi-Hao Ying.Study on reaction diffusion of Zircaloy-2/Chromium system[J].Nuclear Power Engineering,2002,23(3)34-38.
[10]胡赓祥,蔡珣.材料科学基础[M].上海:上海交通大学出版社,2010,124.