YANG Hong-yan,CHEN Huan,ZHANG Rui-qian,WEI Tian-guo,QIU Shao-yu,PENG Xiao-ming.Research Progress of the Surface Coating for Zirconium Alloy Cladding of Accident Tolerant Fuel in Nuclear Power Plant[J],51(7):87-97
Research Progress of the Surface Coating for Zirconium Alloy Cladding of Accident Tolerant Fuel in Nuclear Power Plant
  
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DOI:10.16490/j.cnki.issn.1001-3660.2022.07.008
KeyWord:accident tolerant fuel cladding  Cr coating  deposition technology  performance evaluation
                 
AuthorInstitution
YANG Hong-yan Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
CHEN Huan Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
ZHANG Rui-qian Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
WEI Tian-guo Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
QIU Shao-yu Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
PENG Xiao-ming Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu , China
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Abstract:
      With realizing engineering application easily in the short term, the surface coating of zirconium alloy for accident tolerant cladding has become hotspot in the research and development of latest nuclear fuel elements in the world. This report was about the main research achievements of surface coating on zirconium cladding in recent years. The development of the coating materials on zirconium alloy was reviewed, including Max phase, Cr series, ceramics and FeCrAl alloy. For its high-quality, excellent corrosion resistance and high temperature oxidation resistance, the metal Cr had become the preferred material of zirconium surface coating for accident tolerant cladding. The deposition technology of Cr coating on zirconium alloy were discussed, including physical vapor deposition, cold spraying, laser cladding and plasma spraying. The different technology developments of coated tube for different research institute were mainly analyzed. The key application properties of Cr coating on zirconium alloy were evaluated and the surface coating effects were analyzed especially under high temperature oxidation embrittlement, corrosion, and ring compression, wears and high temperature burst. Cr coating could effectively prevent oxygen diffusing into zirconium alloy in steam environment, and zirconium substrate remained a large amount of β-Zr phase after oxidation test, and the zirconium tube coated Cr still had residual plasticity after high temperature oxidation-quenching test. There were good coordinating deformation between Cr coating and zirconium substrate under small deformation. The burst performances of the coated zirconium tube were improved for surface strengthening effect of Cr coating. After reactor irradiation, the composition and micro-structure of Cr-Zr interface were stable. With 21% expansion due to compression of coated tube after irradiation, the surface Cr coating was still tight. Finally, the research achievements and research directions of Cr coating on zirconium cladding for accident tolerant cladding were summarized and prospected.
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