Effect of Zr on the microstructure of corrosion resistant ODS steels

Zr对耐蚀ODS钢显微组织的影响

• 批准号: EP/M017540/1
• 负责人: Chris Grovenor
• 金额: $ 37万
• 依托单位: University of Oxford
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2016
• 资助国家: 英国
• 起止时间: 2016 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FM017540%2F1
• 关键词: Effect; Zr; microstructure; corrosion; resistant

Radiation-resistant steels are essential for the development of next-generation fission and future fusion energy systems. The incorporation of nano-particles in metallic matrices by powder metallurgy processing is widely employed for the development of radiation-resistant steels, and continues to be the subject of intense research worldwide. The two most critical properties of these materials for application in these future reactor designs are the maintenance of high strength at temperatures above the softening point of conventional steels and the reduction in sensitivity to radiation-induced He embrittlement. Oxide dispersion strengthened (ODS) steels show considerable promise in both properties. The distribution, chemistry and shape of the oxide nanoparticles, and their influence on the matrix chemistry and irradiation response, play a crucial role in many of the improved properties. However, there is considerable disagreement in the literature on the nature of these nanoparticles as a function of alloy chemistry and manufacturing process, and the precise mechanisms by which they respond to irradiation damage. There is also a requirement to develop new ODS steels with improved corrosion resistance specifically for fuel cladding materials for closed fuel cycles. Recently, high Cr ODS steels with Al additions have been developed for use in highly corrosive environments, but their high-temperature strength is poor. First principles calculations by one of the partners indicate that adding Zr to these alloys may refine and increase the number density of oxide particles by forming Y-Zr-O phases. We predict that this would improve the high temperature strength while maintaining the improved corrosion resistance and irradiation performance. It is this prediction that we wish to test in this new project.

耐辐射钢对于下一代裂变和未来聚变能源系统的发展至关重要。通过粉末冶金加工在金属基体中掺入纳米颗粒被广泛用于耐辐射钢的开发，并且仍然是全世界范围内的密集研究的主题。在这些未来的反应堆设计中应用这些材料的两个最关键的特性是在高于常规钢的软化点的温度下保持高强度和降低对辐射引起的He脆化的敏感性。氧化物弥散强化（ODS）钢在这两个性能方面都有相当大的希望。氧化物纳米颗粒的分布、化学性质和形状，以及它们对基质化学和辐射响应的影响，在许多改进的性能中起着至关重要的作用。然而，有相当大的分歧，这些纳米粒子的性质作为合金化学和制造工艺的功能，以及它们响应辐射损伤的精确机制的文献。还需要开发具有改进的耐腐蚀性的新的消耗臭氧层物质钢，专门用于封闭燃料循环的燃料包壳材料。近年来，添加Al的高Cr ODS钢已被开发用于高腐蚀环境，但其高温强度较差。合作伙伴之一的第一性原理计算表明，向这些合金中添加Zr可以通过形成Y-Zr-O相来细化和增加氧化物颗粒的数量密度。我们预测，这将提高高温强度，同时保持改善的耐腐蚀性和辐照性能。我们希望在这个新项目中测试的正是这种预测。

项目成果

Glancing angle XRD analysis of particle stability under self-ion irradiation in oxide dispersion strengthened alloys

• DOI: 10.1016/j.scriptamat.2015.07.037
• 发表时间: 2016-01-01
• 期刊: SCRIPTA MATERIALIA
• 影响因子: 6
• 作者: London, A. J.;Panigrahi, B. K.;Grovenor, C. R. M.
• 通讯作者: Grovenor, C. R. M.