摘要
为了给核燃料后处理硝酸体系的设备腐蚀控制提供理论参考,对000Cr25Ni20超低碳奥氏体不锈钢在40%硝酸中,沸腾和非沸腾(接近沸腾温度)条件下进行腐蚀试验。结果表明,Cr6+和Run+都能显著促进超低碳Cr-Ni奥氏体不锈钢发生过钝化腐蚀和晶间腐蚀;在沸腾条件下,腐蚀更加严重,Run+加速腐蚀作用更大,在非沸腾条件下,2种离子加速腐蚀作用相差不大。
The corrosion resistance of super-low-carbon austenitic stainless steel 000Cr25N20 in boiling and nonboiling(98℃)nitric acid containing Cr6 and Ru^(n+)ions with different concen-trations was investigated,aiming at providing guidance to control the corrosion of nitric acid post-treatment facility for nuclear fuel.It was found that Cr6 and Ru' ions remarkably enhanced the corrosion attack on the stainless steel,which was dominated by o-ver-passivation corrosion and intergranular corrosion.Under boil-ing condition,more serious corrosion attack occurred,and Ru' ion led to more remarkably accelerated corrosion.Under non-boiling condition,the two kinds of ions showed little difference in terms of the accelerating corrosion effect
出处
《材料保护》
CAS
CSCD
北大核心
2009年第2期19-21,83,共3页
Materials Protection