• 主题
高级搜索  >
历史搜索 清空历史
首页> 美国卫生研究院文献>Scientific Reports >Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation
【2h】

Enhanced Radiation-tolerant Oxide Dispersion Strengthened Steel and its Microstructure Evolution under Helium-implantation and Heavy-ion Irradiation

机译：氦离子注入和重离子辐照下增强的耐辐射氧化物弥散强化钢及其组织演变

代理获取
本网站仅为用户提供外文OA文献查询和代理获取服务，本网站没有原文。下单后我们将采用程序或人工为您竭诚获取高质量的原文，但由于OA文献来源多样且变更频繁，仍可能出现获取不到、文献不完整或与标题不符等情况，如果获取不到我们将提供退款服务。请知悉。
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The world eagerly needs cleanly-generated electricity in the future. Fusion reactor is one of the most ideal energy resources to defeat the environmental degradation caused by the consumption of traditional fossil energy. To meet the design requirements of fusion reactor, the development of the structural materials which can sustain the elevated temperature, high helium concentration and extreme radiation environments is the biggest challenge for the entire material society. Oxide dispersion strengthened steel is one of the most popular candidate materials for the first wall/blanket applications in fusion reactor. In this paper, we evaluate the radiation tolerance of a 9Cr ODS steel developed in China. Compared with Ferritic/Martensitic steel, this ODS steel demonstrated a significantly higher swelling resistance under ion irradiation at 460 °C to 188 displacements per atom. The role of oxides and grain boundaries on void swelling has been explored. The results indicated that the distribution of higher density and finer size of nano oxides will lead a better swelling resistance for ODS alloy. The original pyrochlore-structured Y2Ti2O7 particles dissolved gradually while fine Y-Ti-O nano clusters reprecipitated in the matrix during irradiation. The enhanced radiation tolerance is attributed to the reduced oxide size and the increased oxide density.
机译：未来世界急切需要清洁生产的电力。聚变堆是克服传统化石能源消耗造成的环境退化的最理想能源之一。为了满足聚变反应堆的设计要求，可承受高温，高氦气浓度和极端辐射环境的结构材料的开发是整个材料社会面临的最大挑战。氧化物弥散强化钢是聚变反应堆中首批壁/毛毯应用中最受欢迎的候选材料之一。在本文中，我们评估了中国开发的9Cr ODS钢的辐射耐受性。与铁素体/马氏体钢相比，该ODS钢在460°C的离子辐照下每个原子188位移下具有更高的抗溶胀性。已经研究了氧化物和晶界在空隙膨胀中的作用。结果表明，较高密度和较小尺寸的纳米氧化物的分布将导致ODS合金具有更好的溶胀性。原始的烧绿石结构的Y2Ti2O7颗粒逐渐溶解，而细小的Y-Ti-O纳米簇在辐照过程中重新沉淀在基质中。增强的辐射耐受性归因于减小的氧化物尺寸和增加的氧化物密度。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
代理获取

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号