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.

抗辐射钢对于下一代裂变和未来聚变能源系统的开发至关重要。通过粉末冶金加工将纳米颗粒掺入金属基体被广泛用于抗辐射钢的开发，并且仍然是全世界深入研究的主题。这些材料在未来反应堆设计中应用的两个最关键的特性是在高于传统钢软化点的温度下保持高强度以及降低对辐射引起的氦脆化的敏感性。氧化物弥散强化（ODS）钢在这两种性能方面都显示出巨大的前景。氧化物纳米颗粒的分布、化学性质和形状，及其对基质化学和辐照响应的影响，在许多性能改进中发挥着至关重要的作用。然而，文献中对于这些纳米粒子作为合金化学和制造工艺的函数的性质，以及它们响应辐照损伤的精确机制存在相当大的分歧。还需要开发具有改进的耐腐蚀性的新型 ODS 钢，专门用于闭式燃料循环的燃料包壳材料。近年来，已开发出添加Al的高Cr ODS钢，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 相来细化并增加氧化物颗粒的数密度。我们预测这将提高高温强度，同时保持改进的耐腐蚀性和辐照性能。我们希望在这个新项目中测试这一预测。