Cr 涂层锆合金耐事故燃料包壳材料高温蒸汽氧化行为研究进展

Yao Wang, Jinshan Li, Bo Chen, Mingju Chen, Biao Chen, Yi Wang, Weijia Gong

科研成果: 期刊稿件文献综述同行评审

摘要

Accident-tolerant fuel (ATF) can significantly enhance the capability of light-water nuclear reactors to withstand core melting under loss of coolant accident (LOCA), which is a revolutionary development of nuclear fuel technology and nuclear power safety. Cr-coating deposited on the current Zr-based nuclear fuel cladding demonstrates good adhesion, excellent corrosion resistance in high-temperature and high-pressure water, and high-temperature oxidation resistance. Therefore, Cr-coated zirconium alloys emerge as the most promising ATF solution for practical engineering application in nearest future. The present paper reviewed the research progress on oxidation behavior of Cr-coated zirconium alloy in high-temperature steam environment. The oxidation kinetics of the Cr coating, the effect of microstructure on the anti-oxidation performance of the Cr coating, the failure mechanism of the Cr coating after long-term oxidation and the Cr-Zr interdiffusion behavior were discussed. Additionally, strategies for enhancing the anti-oxidation performance of the Cr coating and suppressing Cr-Zr interdiffusion were summarized, and future development directions were prospected, aiming to provide references for the optimization design and engineering application of Cr-coated Zr-based nuclear fuel cladding.

投稿的翻译标题Research Progress on High-Temperature Steam Oxidation Behavior of Cr-Coated Zirconium Alloy as Accident-Tolerant Fuel Cladding
源语言繁体中文
页(从-至)3271-3280
页数10
期刊Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering
53
11
DOI
出版状态已出版 - 11月 2024

关键词

  • accident-tolerant fuel
  • Cr-coating
  • high-temperature steam oxidation
  • microstructure
  • zirconium alloy cladding

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