NSERC/UNENE Industrial Research Chair in Nuclear Materials
NSERC/UNENE 核材料工业研究主席
基本信息
- 批准号:345857-2016
- 负责人:
- 金额:$ 17.92万
- 依托单位:
- 依托单位国家:加拿大
- 项目类别:Industrial Research Chairs
- 财政年份:2019
- 资助国家:加拿大
- 起止时间:2019-01-01 至 2020-12-31
- 项目状态:已结题
- 来源:
- 关键词:
项目摘要
The Industrial Research Chair program supports the life management of the fuel channel, a key mechanicalsystem in a CANDU(R) nuclear power reactor. It supports the CANDU Owner's Group R&D program toaddress life management issues in the existing fleet of 27 operating reactors, as well as research programs atCandu Energy and Canadian Nuclear Laboratories to develop improved fuel channel materials and designs forrefurbishment of both existing plants and for future CANDU power plants in the short, medium and long term.The purpose is to further the fundamental understanding of nuclear materials and to develop applied technologyrequired by the industry in this area. This includes radiation-induced deformation of nuclear materials(especially zirconium alloys), the fracture properties of such materials and the relationship of properties tomanufacturing variables, crystallographic texture and microstructure.There are five major research themes:1.Experimental studies of the deformation of Zr alloys (plasticity, creep, fatigue)2.Effect of irradiation: a) on the deformation and microstructure of Zr and Ni alloys, and b) on fracture(fatigue, hydride properties, DHC)3.Effects of hydrides on the properties of Zr alloys4.Modelling: a) of deformation, and b) of effect of hydrides on Zr alloys5.Control of microstructure and texture of alpha-beta zirconium alloys.The program also serves to train graduate students in an area where there is a strong demand for expert HQP.
工业研究教席计划支持燃料通道的寿命管理,燃料通道是CANDU(R)核动力反应堆中的关键机械系统。它支持CANDU所有者的集团研发计划,以解决现有27个运行中的反应堆机队的寿命管理问题,以及坎杜能源和加拿大核实验室的研究计划,以开发改进的燃料通道材料,并为两个现有工厂和未来的CANDU发电厂的短期、中期和长期翻新设计。目的是加深对核材料的基本了解,并开发该行业在这一领域所需的应用技术。这包括核材料(特别是锆合金)的辐照变形、这类材料的断裂性能以及性能与制造变量、晶体织构和微观结构之间的关系。主要研究内容有五个:1.锆合金变形(塑性、蠕变、疲劳)的实验研究2.辐照对锆和镍合金变形和组织的影响;b)对断裂的影响(疲劳、氢化物性能、DHC)3.氢化物对锆合金性能的影响4)变形模型:a)变形和b)氢化物对锆合金的影响5.α-β锆合金的组织和织构的控制。该计划还用于在对专家HQP有强烈需求的领域培养研究生。
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:
$ 17.92万 - 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
- 批准号:
RTI-2022-00450 - 财政年份:2021
- 资助金额:
$ 17.92万 - 项目类别:
Research Tools and Instruments
Mechanistic understanding of hydrided region overload cracking
氢化区过载开裂的机理理解
- 批准号:
556184-2020 - 财政年份:2021
- 资助金额:
$ 17.92万 - 项目类别:
Alliance Grants
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:2021
- 资助金额:
$ 17.92万 - 项目类别:
Discovery Grants Program - Individual
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:2020
- 资助金额:
$ 17.92万 - 项目类别:
Discovery Grants Program - Individual
NSERC/UNENE Industrial Research Chair in Nuclear Materials
NSERC/UNENE 核材料工业研究主席
- 批准号:
345857-2016 - 财政年份:2020
- 资助金额:
$ 17.92万 - 项目类别:
Industrial Research Chairs
Mechanistic understanding of hydrided region overload cracking
氢化区过载开裂的机理理解
- 批准号:
556184-2020 - 财政年份:2020
- 资助金额:
$ 17.92万 - 项目类别:
Alliance Grants
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