Study on Corrosion Resistance of Zr-0.8Sn-1Nb-0.3Fe Alloy after Kr~+ Ion Irradiation

Abstract

采用高压釜腐蚀实验研究了2种不同制备工艺下的Zr-0.8Sn-1Nb-0.3Fe合金(1#,2#)经360℃、5~25; dpa的Kr~+辐照后、在400℃/10.3 MPa过热蒸汽中的耐腐蚀性能,用透射电子显微镜(TEM)、扫描电镜(SEM)、; X射线衍射仪(XRD)分析合金腐蚀后氧化膜显微组织结构。结果表明,100; d腐蚀后,合金的腐蚀增重随着辐照剂量的增加而增加,由于1#合金中的第二相比2#合金更为细小、弥散,相同辐照剂量下,前者的腐蚀增重较低。腐蚀转折前; ,从蒸汽腐蚀侧到锆合金基体,氧化膜中的氧含量逐渐降低,靠近蒸汽侧的氧化膜主要由等轴晶形态的单斜ZrO_2组成,而基体界面处的氧化膜主要为柱状晶形; 态的四方ZrO_2和六方Zr_3O;腐蚀转折后,基体界面处的氧化膜呈"花菜"状生长,"花菜"尺寸大小与氧化膜生长速率的高低及不均匀生长趋势的大小; 呈对应关系。The corrosion resistance of Zr-0.8Sn-1Nb-0.3Fe alloys prepared by two; different processes was investigated in 400℃/18.6MPa superheated steam; by static autoclave after irradiated by 360℃ with Kr~+-irradiation of; 5~25 dpa. The microstructures of oxidation film after corrosion were; analyzed by TEM, SEM, and XRD. The results showed that the corrosion; weight-gain increased with the irradiation dose, while the weight-gain; of 1# alloy with smaller and more dispersive SPPs than 2# alloy was; lower under the same irradiation dose. Before corrosion turning, the; oxygen content in the oxidation film decreased from the steam-side to; the zirconium matrix. The oxidation film beside the steam-side was; mainly composed by equiaxied monoclinic ZrO_2 crystal, while near the; film/matrix interface by columnar quartet ZrO_2 crystal and hexagonal; Zr_3O crystal. After transition of corrosion weight, the film near the; interface grew like cauliflowers, and the size of cauliflowers were; corresponded to the growth rate and uneven growth trend of oxidation; film

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