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 |
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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 |
卷 | 53 |
期 | 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