Effect of local microstructure on cracking of materials for next generation reactors
局部微观结构对下一代反应堆材料开裂的影响
基本信息
- 批准号:RGPIN-2020-03904
- 负责人:
- 金额:$ 5.54万
- 依托单位:
- 依托单位国家:加拿大
- 项目类别:Discovery Grants Program - Individual
- 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:
- 关键词:
项目摘要
The global drive for low-carbon energy sources, combined with a growing worldwide energy consumption, is a challenge to which nuclear energy, in combination with renewables such as wind and solar, provides a realistic, sustainable solution. Canada aims to position itself at the forefront of advanced nuclear reactor designs, with substantial investment in the development of small nuclear modular reactors (SMRs). However, SMRs are still a decade from implementation, and a range of urgent questions must first be answered. Many of the limitations to SMR delivery arise from materials issues: how they will respond, age and fail under the conditions they will experience. This proposal will address key basic research questions into material performance, which will be required to enable safe SMR operation. Specifically, it will investigate the damage processes associated with irradiation in SMR-proposed materials, and the subsequent effect on fracture and especially fatigue of SMR-relevant metals. Real materials are made up of grains or crystallites - each individual crystallite is typically highly anisotropic in its response to stress. In many practical applications we cannot ignore this local heterogeneity and must understand how irreversible microstructural changes occur and propagate at this local scale. Diffraction techniques are able to reveal many of the microstructural changes which will have an influence, including inter-granular strains induced by elastic and plastic crystallographic anisotropy, intra-granular strains generated by crystallographic defects (dislocations), as well as deformation-induced phase transformations or crystallographic reorientation. The aim of this proposal is to investigate the extent to which monitoring these effects can provide insights into understanding the mechanisms of fatigue and the processes of initial crack propagation. In addition, we will investigate the way that irradiation influences microstructural damage accumulation. While temperature and stress provide two key variables that influence material properties, they are not the only ones. Materials behave differently in an energetic radiation environment (e.g., in a nuclear reactor or in space) than in conventional applications due to the flux of high energy particles which introduce point defects and dislocations, and alter the microchemistry of the material. This proposal will train HQP directly in advanced techniques (both experimental and modeling) and in a research area which is of current and ongoing interest to a wide range of industry, not just nuclear power. Building on existing successes, it will strive to deliver a diverse group of HQP with skills and knowledge that will be valuable to Canadian industry.
全球对低碳能源的推动,加上全球能源消费的不断增长,是一个挑战,核能与风能和太阳能等可再生能源相结合,提供了一个现实的,可持续的解决方案。加拿大的目标是使自己处于先进核反应堆设计的最前沿,并在小型核模块反应堆的开发方面进行大量投资。然而,《工作人员-管理层关系》距离实施还有十年的时间,必须首先回答一系列紧迫的问题。对SMR交付的许多限制来自材料问题:它们将如何响应,在它们将经历的条件下老化和失败。该提案将解决材料性能的关键基础研究问题,这将是确保SMR安全运行所必需的。具体而言,它将调查与SMR提出的材料中的辐照相关的损伤过程,以及随后对SMR相关金属的断裂,特别是疲劳的影响。 真实的材料由晶粒或微晶组成-每个单独的微晶在其对应力的响应中通常是高度各向异性的。在许多实际应用中,我们不能忽视这种局部异质性,必须了解不可逆的微观结构变化是如何在这种局部尺度上发生和传播的。衍射技术能够揭示许多将产生影响的微观结构变化,包括由弹性和塑性晶体各向异性引起的晶粒间应变、由晶体缺陷(位错)产生的晶粒内应变以及变形引起的相变或晶体重定向。 本建议的目的是调查在何种程度上监测这些影响可以提供深入了解疲劳的机制和初始裂纹扩展的过程。此外,我们将调查的方式,辐照影响微结构损伤积累。虽然温度和应力是影响材料性能的两个关键变量,但它们并不是唯一的变量。材料在高能辐射环境中表现不同(例如,在核反应堆中或在太空中),这是由于引入点缺陷和位错并改变材料的微观化学性质的高能粒子的通量。该提案将直接在先进技术(实验和建模)和研究领域对HQP进行培训,该研究领域对广泛的行业(而不仅仅是核电)具有当前和持续的兴趣。在现有成功的基础上,它将努力提供一个多元化的HQP组的技能和知识,将是宝贵的加拿大工业。
项目成果
期刊论文数量(0)
专著数量(0)
科研奖励数量(0)
会议论文数量(0)
专利数量(0)
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{{ truncateString('Daymond, Mark', 18)}}的其他基金
Effect of local microstructure on cracking of materials for next generation reactors
局部微观结构对下一代反应堆材料开裂的影响
- 批准号:
RGPIN-2020-03904 - 财政年份:2022
- 资助金额:
$ 5.54万 - 项目类别:
Discovery Grants Program - Individual
Characterizing Irradiation Degradation in Nuclear Power Systems: Eliminating Artefacts
表征核电系统中的辐照退化:消除伪影
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Mechanistic understanding of hydrided region overload cracking
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Effect of local microstructure on cracking of materials for next generation reactors
局部微观结构对下一代反应堆材料开裂的影响
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RGPIN-2020-03904 - 财政年份:2020
- 资助金额:
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