辐照损伤影响低活化铁素体/马氏体钢高温水腐蚀行为的机理研究

从压水堆到第四代超临界水堆，材料面临高剂量的辐照和高温水的腐蚀。研究理解在辐照环境下核材料的腐蚀退化机制并预测其服役行为对水冷堆的安全和发展有重要意义。低活化铁素体/马氏体钢具有优良的抗辐照性能和抗腐蚀性能，是超临界水冷堆等先进核能系统的候选结构材料。在水冷堆的强辐照和腐蚀环境中，辐照损伤引起结构材料抗腐蚀性能的退化机制是需要重点关注的科学问题。本项目以低活化铁素体/马氏体钢为研究对象，采用低能和高能离子辐照材料引入微观缺陷，重点研究微观缺陷对低活化铁素体/马氏体钢高温水腐蚀的影响以及其腐蚀氧化膜的辐照性能的变化规律，探索辐照与高温高压水腐蚀互相作用机理。通过研究低活化铁素体/马氏体不锈钢在辐照环境下的抗腐蚀性能的退化和相关机制，为先进水冷堆候选结构材料抗腐蚀性能研究提供重要的数据参考。

From pressurized water reactor to the generation Ⅳ supercritical water reactor, the materials are exposed to high dose irradiation and high-temperature water corrosion environments. It is of great significance to understand the corrosion degradation mechanism of nuclear materials under irradiation environment and predict their service behaviour for the safety and development of water-cooled reactors. Due to the good irradiation and corrosion resistance, low activated ferrite/martensitic (RAFM) steel is a candidate structural material for advanced nuclear power systems such as supercritical water reactor. In the highly radioactive and severe corrosive environment of water-cooled reactor, the degradation mechanism of corrosion resistance of structural materials caused by radiation damage is an important scientific issue. In this project RAFM steel will be irradiated by low energy and high energy ion, we will study the influence of irradiation damage on corrosion behavior of RAFM steel and investigate the irradiation damage of oxide film, and explore the mechanism of interaction between irradiation and corrosion in high temperature water. This research will provide important data for the study of corrosion resistance of candidate structural materials in advanced water cooled reactor, through investigating the degradation of corrosion resistance of RAFM steel under irradiation.