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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℃、5~25dpa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 autoclave corrosion experiments were carried out to investigate the effect of Zr-0.8Sn-1Nb-0.3Fe alloy (1 #, 2 #) under 360 ℃ and 5 ~ 25dpa Kr + irradiation at 400 ℃ / 10.3 MPa superheated steam. The microstructure of the oxide film was analyzed by transmission electron microscopy (TEM), scanning electron microscopy (SEM) and X-ray diffraction (XRD). The results show that after 100 days of corrosion, the corrosion weight gain of the alloy increases with the increase of the irradiation dose. Since the second phase of the # 1 alloy is more fine and dispersive than the # 2 alloy, the former Corrosion weight gain is low. Before the corrosion transition, the oxygen content in the oxide film decreased gradually from the steam corrosion side to the zirconium alloy substrate. The oxide film near the steam side mainly consisted of monoclinic ZrO 2 with equiaxed grain morphology. The oxide film at the interface of the matrix was mainly columnar The morphology of the tetragonal ZrO 2 and hexagonal Zr 3 O 3 showed that the oxide film at the interface of the substrate showed “Cauliflower” -like growth, the size of “Cauliflower” and the growth rate of the oxide film and the non-uniform growth tendency Corresponding relationship.