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

核材料在高温和熔盐中的机械和腐蚀研究

• 批准号: 580456-2022
• 负责人: Zou, YuY
• 金额: $ 8.74万
• 依托单位: University of Toronto
• 依托单位国家: 加拿大
• 项目类别: Alliance Grants
• 财政年份: 2022
• 资助国家: 加拿大
• 起止时间: 2022-01-01 至 2023-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=758241
• 关键词: Mechanical; corrosion; studies; nuclear; materials

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.

正在开发小型模块化反应堆（SMR），以满足全球对安全，清洁，经济能源的需求。与传统的CANDU反应堆相比，SMR需要在更苛刻的条件下运行的材料-在更高的温度和压力以及更腐蚀的环境中。不幸的是，在这些条件下的材料行为的数据严重缺乏。这是对SMR进行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°C的高温下以及在熔融的氟化物（F）和氯化物（Cl）盐中检查典型的铁基和镍基核材料。我们将开展腐蚀、蠕变断裂、应力腐蚀开裂和腐蚀疲劳试验，并提供合格的数据，以支持监管决策和监督。