Stress corrosion cracking (SCC) of FeCrNi alloys and IASCC of stainless steels: evaluation using micro-mechanical testing techniques

FeCrNi 合金的应力腐蚀开裂 (SCC) 和不锈钢的 IASCC：使用微机械测试技术进行评估

• 批准号: 536313-2018
• 负责人: Persaud, Suraj
• 金额: $ 4.44万
• 依托单位: Queen's University
• 依托单位国家: 加拿大
• 项目类别: Collaborative Research and Development Grants
• 财政年份: 2021
• 资助国家: 加拿大
• 起止时间: 2021-01-01 至 2022-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=720125
• 关键词: Stress; corrosion; cracking; SCC; FeCrNi

Nuclear power is a carbon-free energy source that currently provides 60% of the electrical power in Ontario. While the reduction in greenhouse gas emissions is promising, aging nuclear power plants (NPP) in Canada present safety and economic concerns that must be continuously addressed. Paramount to these concerns is the corrosion and degradation of NPP components, which result in costly forced outages for Canadian utilities and, in the worst case, material failure during operation can have severe safety implications for the general public. Metals and alloys in NPPs are required to operate in aggressive environments which are complicated by several variables, such as environment chemistry and irradiation damage. To ensure safe and reliable operation of Canadian NPPs well into the future, the behaviour of nuclear materials in these environments must be understood. Canadian nuclear utilities are particularly interested in this research as reactors approach 60 years, and with the desire for life extension up to 100 years.In partnership with Canadian nuclear utilities, this program aims to develop a fundamental understanding of the mechanical properties of irradiated materials, and evaluate the possibility of cracking at micro-scale, compromised regions. Our novel approach involves application of in-situ micro-mechanical testing techniques, developed in the past 15 years, to evaluate the mechanical behaviour of nuclear materials at the micro-scale. This innovative research is enabled by the combined corrosion testing infrastructure, and state-of-the-art proton accelerator and microscopy facilities available at Queen's University. Materials and environments are selected to simulate Canadian NPP conditions. This innovative approach is particularly well suited to studying nuclear materials with high radiation fields, and helps develop our understanding of materials issues that may arise in current Canadian NPPs or with life extension. Also, HQP will have many opportunities to interact with industry, research practical problems, and develop multi-disciplinary skills.

核电是一种无碳能源，目前提供安大略省 60% 的电力。 虽然温室气体排放量的减少是有希望的，但加拿大老化的核电站（NPP）带来了安全和经济问题，必须不断解决。 这些问题中最重要的是核电站部件的腐蚀和退化，这会导致加拿大公用事业公司被迫停电，代价高昂，而且在最坏的情况下，运行期间的材料故障可能会对公众产生严重的安全影响。 核电厂中的金属和合金需要在恶劣的环境中运行，这些环境因环境化学和辐射损伤等多种变量而变得复杂。 为了确保加拿大核电站在未来安全可靠地运行，必须了解核材料在这些环境中的行为。加拿大核电公司对这项研究特别感兴趣，因为反应堆的寿命已接近 60 年，并且希望将寿命延长至 100 年。该计划与加拿大核电公司合作，旨在对辐照材料的机械性能有一个基本的了解，并评估微尺度、受损区域开裂的可能性。 我们的新颖方法涉及应用过去 15 年开发的原位微机械测试技术，以评估核材料在微观尺度上的机械行为。 这项创新研究是通过女王大学综合腐蚀测试基础设施以及最先进的质子加速器和显微镜设施来实现的。 选择材料和环境来模拟加拿大核电站的条件。这种创新方法特别适合研究高辐射场的核材料，有助于加深我们对当前加拿大核电站或寿命延长可能出现的材料问题的理解。 此外，HQP 将有很多机会与行业互动、研究实际问题并培养多学科技能。