摘要
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 corrosion resistance of Zr-0.8Sn-lNb-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 ZrO2 crystal, while near the film/matrix interface by columnar quartet ZrO2 crystal and hexagonal Zr30 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.
作者
杨忠波
程竹青
邱军
吴宗佩
张海
冉广
Yang Zhongbo Cheng Zhuqing Qiu Jun Wu Zongpeil Zhang Hai Ran Guang(Science and Technology on Reactor Fuel and Materials LaboratOry, Nuclear Power Institute of China, Chengdu, 610213, China College of Energy, Xiamen University, Xiamen, Fujian, 361102, China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2017年第5期123-128,共6页
Nuclear Power Engineering
