Zr-1Sn-1Nb-0.3Fe合金腐蚀模型研究

Study on Corrosion Model for Zr-1Sn-1Nb-0.3Fe Zirconium Alloy

包壳材料是燃料组件设计研究的重点,而限制包壳材料的主要特性则是其腐蚀性能。锆合金腐蚀机理较为复杂,中子辐照条件对锆合金腐蚀又会产生不确定的影响,仅依赖堆外腐蚀试验难以评定锆合金的腐蚀性能并建立理论模型。本文通过结合Zr-1Sn-1Nb-0.3Fe合金堆内腐蚀试验结果首次建立了Zr-1Sn-1Nb-0.3Fe合金腐蚀模型。

Cladding material is the focus in the fuel assembly design, and the main characteristics that limit the cladding material is its corrosion performance. The corrosion mechanisms in zirconium alloys is complicated, and the neutron irradiation condition causes uncertain effects on the corrosion of zirconium alloys, and thus, it is difficult to estimate the zirconium alloy corrosion behavior and build the corrosion model just based on the out-pile corrosion test. In this paper, the corrosion model is built for the first time by analyzing the in-pile corrosion test results for Zr-1Sn-1Nb-0.3Fe. © 2015, Editorial Office of Nuclear Power Engineering. All right reserved.