Mechanical and corrosion studies of nuclear materials at elevated temperatures and in molten salts

小型模块化反应堆(SMR)正在开发，以满足全球对安全、清洁、经济能源的需求。与传统的CANDU反应堆不同，SMR要求材料在更恶劣的条件下运行--在更高的温度和压力下，以及在更具腐蚀性的环境中。不幸的是，关于这些条件下的物质行为的数据严重缺乏。这是向SMR发放部署许可的主要障碍。在这个项目中，我们将提供关于SMR中核材料降解机制的关键数据。我们的团队将在高达1,000摄氏度的高温下以及熔融的氟(F)和氯(Cl)盐中研究典型的铁基和镍基核材料。开展腐蚀、蠕变断裂、应力腐蚀和腐蚀疲劳试验，为监管决策和监督提供合格数据。

Small Modular Reactors (SMRs) are being developed to tackle the global need for safe, clean, economical energy. In contrast to traditional CANDU reactors, SMRs require materials to operate in more severe conditions - at higher temperatures and pressures and in more corrosive environments. Unfortunately, data about material behaviour in these conditions are severely lacking. This is a major barrier to ever licensing SMRs for deployment. In this project, we will produce critical data on the degradation mechanisms of nuclear materials in SMRs. Our team will examine typical Fe- and Ni-based nuclear materials at elevated temperatures up to 1,000°C and in molten fluoride (F) and chloride (Cl) salts. We will carry out corrosion, creep rupture, stress corrosion cracking, and corrosion fatigue tests and provide qualified data to support regulatory decision-making and oversight.