超临界水堆候选材料的腐蚀特性研究

Corrosion Behaviors of Candidate Materials for Supercritical-Cooled Water Reactor

对铁素体/马氏体(F/M)耐热钢P92、奥氏体不锈钢316L和镍基合金690在600℃、23MPa超临界水中的腐蚀行为进行了研究。在600℃、23MPa的超临界水中腐蚀625h后,690合金、316L不锈钢和P92耐热钢的腐蚀增重速率分别为0.00102、0.0606、0.10127g/(m2·h)。用扫描电子显微镜(SEM)进行观察后发现,超临界环境下F/M耐热钢P92的氧化膜为3层结构,奥氏体不锈钢316L的氧化膜为单层结构,镍基合金690表面生成了一层极薄且有点蚀的氧化膜。

The corrosion behaviors of ferritic-martensitic steel P92, austenitic stainless steel type 316L and nickel-based alloy 690 have been investigated in supercritical water （SCW） at 600℃ and 23 MPa. After exposed to SCW for 625 h, the weight gain of alloy 690, 316L and P92 are 0.001 02 g/（m^2·h）, 0.060 6 g/（m^2·h） and 0.101 27g/（m^2·h）, respectively. SEM observation shows that a three-layer oxide film is formed on P92, a single-layer oxide film is formed on 316L and a very thin oxide film with some pitting is formed on alloy 690.