| CAO Guo-qin,REN Ying-ying,WU Kang-kang,YAO Hang-hang,HU Jun-hua,SHAO Guo-sheng,YUAN Gai-huan.Life Extension Strategy and Research Progress of Zirconium Alloy Cladding Applied to Light Water Reactors[J],48(11):69-81 |
| Life Extension Strategy and Research Progress of Zirconium Alloy Cladding Applied to Light Water Reactors |
| Received:July 23, 2019 Revised:November 20, 2019 |
| View Full Text View/Add Comment Download reader |
| DOI：10.16490/j.cnki.issn.1001-3660.2019.11.007 |
| KeyWord:cladding materials zirconium alloy coating oxidative corrosion irradiation resistance element migration |
| Author | Institution |
| CAO Guo-qin |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China |
| REN Ying-ying |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China |
| WU Kang-kang |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China |
| YAO Hang-hang |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China |
| HU Jun-hua |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China; 3.Zhengzhou Materials Genome Institute, Xingyang , China |
| SHAO Guo-sheng |
1.School of Materials Science and Engineering, Zhengzhou University, Zhengzhou , China; 2.State Centre for International Cooperation on Designer Low-carbon & Environmental Materials, Zhengzhou , China; 3.Zhengzhou Materials Genome Institute, Xingyang , China |
| YUAN Gai-huan |
4. State Nuclear Baoti Zirconium Industry Co., Ltd SNZ, Baoji , China |
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| Abstract: |
| The research status of coating technology for zirconium alloys applied to nuclear reactors was summarized. Non-metallic coatings, metal coatings and MAX coatings were discussed. Among them, the MAX phase combined the advantages of metal properties and ceramic properties. The corrosion behavior of the cladding materials in normal service environment was analyzed, including the superheated water corrosion under normal conditions and the corrosion behavior in aqueous solution containing lithium ions. Moreover, the ion irradiation behavior and the high temperature steam corrosion behavior under accident conditions were also considered. The researches on existing coating materials generally have limitations, which mainly focuses on high-temperature steam corrosion. Some new materials have emerged, such as MAX phase and silicon coatings that can form dense oxide film in the oxidation process. However, the application under normal conditions is unknown. Metal coatings have better advantages in corrosion resistance, but their anti-irradiation behavior and neutron economy need to be studied. At present, single layer coatings can not meet the corrosion resistance and high stability under normal conditions and high temperature steam on the basis of satisfying the radiation resistance and neutron economy. The composite coatings or multilayer coating technologies gradually begin to gain attention. The kinetic behavior of element migration in multi-component coatings during oxidation process and the micro alloying of the interface between coating and substrate have far-reaching significance. At present, the research in this area remains to be broken through. |
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