Effect of Zr on the microstructure of corrosion resistant ODS steels

Zr对耐蚀ODS钢显微组织的影响

基本信息

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

项目摘要

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.

抗辐射钢对于开发下一代裂变和未来的融合能系统至关重要。通过粉末冶金加工将纳米粒子掺入金属矩阵中，广泛用于开发耐辐射钢，并继续是全球强烈研究的主题。这些材料在这些未来的反应堆设计中的应用是在传统钢的软化点上方的高强度以及对辐射引起的敏感性的降低时的高强度。氧化物分散剂加强（ODS）钢在这两种特性中都表现出巨大的希望。氧化物纳米颗粒的分布，化学和形状及其对基质化学和辐照反应的影响在许多改进的特性中起着至关重要的作用。但是，关于这些纳米颗粒的性质的文献存在很大的分歧，这是合金化学和制造过程的函数，以及它们对辐射损害做出反应的确切机制。还需要开发新的ODS钢，具有改进的耐腐蚀性，专门针对封闭燃料循环的燃料覆层材料。最近，已经开发出高CR ODS钢，用于在高度腐蚀性的环境中使用，但它们的高温强度很差。一位合作伙伴的第一原理计算表明，将ZR添加到这些合金中可能会通过形成Y-ZR-O相通过形成氧化物颗粒的数量来提高并增加氧化物颗粒的数量密度。我们预测，这将提高高温强度，同时维持改善的耐腐蚀性和辐射性能。正是我们希望在这个新项目中测试的这一预测。