摘要
尝试模拟核电压力容器筒体外表面在电厂运行期间所形成氧化膜的粗糙度、表面形貌、物相成分、层次结构、氧化增重速率等特征参数,对压力容器筒体用材进行模拟运行环境工况的高温氧化试验,对比不同初始状态的试样表面形成的氧化膜的差异,以获得贴近实际情况的氧化产物。研究数据表明,压力容器材料属于完全抗氧化类,且高温试验前未锈蚀氧化与高温试验前锈蚀氧化的数据存在一定的差异,该研究为熔融物堆内滞留方案提供有效数据。
This paper attemps to simulate the characteristic parameters of the oxide film formed during plant operation at the outer surface of nuclear reactor vessel,such as roughness,surface topography,phase composition,layer stucture,oxidative weight gain rate. By doing high temperature oxidation simulating test on reactor vessel material,and comparing the difference between samples with various original states,to acquire the oxidation product similar to the actual situation. The analysis showed that the reactor vessel material is completely antioxidant,and there is difference between the data of samples uncorroded before high temperature test and the data of corroded ones,thus giving effective data for the solution of molten corium in-vessel retention( IVR).
出处
《压力容器》
北大核心
2018年第1期7-14,共8页
Pressure Vessel Technology
