Abstract
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.
| Translated title of the contribution | Research Progress on High-Temperature Steam Oxidation Behavior of Cr-Coated Zirconium Alloy as Accident-Tolerant Fuel Cladding |
|---|---|
| Original language | Chinese (Traditional) |
| Pages (from-to) | 3271-3280 |
| Number of pages | 10 |
| Journal | Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering |
| Volume | 53 |
| Issue number | 11 |
| DOIs | |
| State | Published - Nov 2024 |