Inconel 601合金在高温硼硅酸盐核废物玻璃熔体中的腐蚀行为

Corrosion behavior of Inconel 601 alloy in high-temperature borosilicate glass melts containing simulant nuclear waste

研究了Inconel 601合金在普通硼硅酸盐核废物玻璃(MW)和添加ZnO、Mn_2O_3改性的硼硅酸盐玻璃(MZMF)的1060℃高温熔体中浸泡168 h和336 h的腐蚀行为,利用扫描电子显微镜和能谱仪、X射线衍射分析仪,研究了合金与玻璃的腐蚀界面的表面形貌、元素组成以及相结构变化。结果表明:合金表面生成了Cr_2O_3层,其中合金在MW中的腐蚀深度比在MZMF中大10μm;在MW熔体中,MgO、Fe_2O_3和Cr_2O_3反应生成MgCr_2O_4和FeCr_2O_4,破坏了合金和玻璃之间的Cr_2O_3层,使该层呈碎片状。在MZMF高温熔体中长期浸泡后,合金表面形成的Cr_2O_3层呈连续均匀的状态,并且Cr_2O_3层外附着一层含B、O、Fe、Mn、Zn的锯齿状化合物,阻碍了Cr_2O_3层与MgO或其他化学物质反应,减缓了合金的腐蚀速率。

The corrosion behaviors of Inconel 601 alloy immersed in the borosilicate glass（ MW glass） and in ZnO,Mn2O3 modified borosilicate glasses（ MZMF glass） containing simulant nuclear waste at 1060 ℃ for 168 h and 336 h were studied. The surface morphology,chemical composition of elements and the change of phase structure of the corrosion interface between the alloy and glass were studied by means of scanning electron microscopy（ SEM）,energy disperse spectroscopy（ EDS） and X-ray diffraction（ XRD）. The results show that the Cr2O3 layer is formed on the alloy surface,and the corrosion depth of the Inconel 601 in MW waste glass melt is about 10μm greater than that in the MZMF glass melt. In the MW glass,the Cr2O3 layer between the alloy and glass is fragmented because of the reaction among MgO,Fe2O3 and Cr2O3,which forms the crystal phase MgCr2O4 and FeCr2O4. After immersing in the MZMF waste glasses for long time,the Cr2O3 layer formed on the surface of the alloy shows a continuous uniform state,and a thin（ B,O,Fe,Mn,Zn）-containing zigzag layer formed on the surface of the Cr2O3 layer may prevent Cr2O3 from reacting with MgO or other constituents,and slow down the corrosion rate of the Inconel 601 alloy.