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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。
The cladding material is the focus of fuel assembly design and research, and the main characteristics that limit cladding material are their corrosion properties. The corrosion mechanism of zirconium alloy is more complicated. The influence of neutron irradiation conditions on the corrosion of zirconium alloy will have an indefinite influence. It is difficult to evaluate the corrosion performance of zirconium alloy only based on the corrosion test outside the reactor and to establish a theoretical model. In this paper, the corrosion model of Zr-1Sn-1Nb-0.3Fe alloy was established for the first time by combining the results of in-reactor corrosion test of Zr-1Sn-1Nb-0.3Fe alloy.