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.

核能是一种无碳能源，目前为安大略省提供了60%的电力。虽然减少温室气体排放是有希望的，但加拿大老化的核电站（NPP）带来了必须不断解决的安全和经济问题。这些担忧中最重要的是NPP组件的腐蚀和退化，这将导致加拿大公用事业公司昂贵的强制停机，在最坏的情况下，运行期间的材料故障可能会对公众造成严重的安全影响。核电站中的金属和合金需要在恶劣的环境中运行，这种环境由于环境化学和辐射损伤等多种因素而变得复杂。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，因为反应堆的寿命接近60年，并希望将寿命延长到100年。该项目与加拿大核能公用事业公司合作，旨在对辐照材料的机械特性有一个基本的了解，并评估在微观尺度、受损区域开裂的可能性。我们的新方法包括应用过去15年来发展起来的原位微力学测试技术来评估核材料在微观尺度上的力学行为。这项创新研究是由皇后大学的腐蚀测试基础设施、最先进的质子加速器和显微镜设备所实现的。材料和环境的选择是为了模拟加拿大核电站的条件。这种创新的方法特别适合研究具有高辐射场的核材料，并有助于加深我们对当前加拿大核电站或延长寿命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，并发展多学科技能。