| 英文摘要 |
Zirconium alloys are widely used as sheath materials in nuclear power plants because of their good corrosion resistance in water chemistry environment, low thermal capture cross-section of neutron, and good mechanical properties. However, when an accident occurs, especially in the event of loss of cooling water, the temperature of the reactor core will continue to rise. Zr-based alloys will lose their corrosion resistance and react violently with the steam to produce zirconia and hydrogen. In addition to the damage of the cladding itself, which will lead to the leakage of the fission product, the released hydrogen can also cause hydrogen explosion. Therefore, it is a very important issue to improve the corrosion resistance of zirconium alloy cladding materials at high temperatures. In this study, we used an unbalanced magnetron sputtering system to deposit a chromium nitride film on Zircaloy-4 substrate, and studied the oxidation resistance of the coated Zircaloy-4 in a high-temperature steam environment of 400 ℃ for 2, 4, and 6 days. The results show that the weight gain of the Zircaloy-4 can be reduced by nearly 90% using CrN coatings in a high-temperature steam environment at 400 ℃. Moreover, the CrN-coated samples still maintain similar microstructure after oxidation tests, while the uncoated samples form a zirconium dioxide layer on the surface with several microns in thickness, and several cracks are also found in the zirconium dioxide layer. This study suggests that the chromium nitride coating can improve the high temperature oxidation resistance of Zircaloy-4. |