首页> 外文期刊>Transactions of the Indian Institute of Metals >A perspective on creep and fatigue issues in sodium cooled fast reactors
【24h】

A perspective on creep and fatigue issues in sodium cooled fast reactors

机译:钠冷快堆的蠕变和疲劳问题透视

获取原文
获取原文并翻译 | 示例
       

摘要

Development of advanced materials alongwith improved high temperature mechanical properties, particularly creep and fatigue are important and play a major role for the successful development of robust, safe and economical sodium cooled fast reactor (SFR) technology. The components of SFRs operate in demanding environments at high temperatures under complex creep, fatigue and creep-fatigue loading conditions. Based upon the service requirements in terms of different environments, temperature and loading conditions, different materials are chosen for different components. Ti modified 15Cr-15Ni austenitic stainless steel is chosen for clad and wrapper tubes in the reactor core, which experience high fast neutron flux of ∼ 1015 ncm−2s−1 along with high temperatures. Type 316L(N) SS is used for out-of-core structural components like main and inner vessels, and sodium pipelines. For steam generators, modified 9Cr-1Mo steel is chosen for all the components, where liquid sodium and steam/water coexist. Some of the important experiences and exciting achievements in the areas of in-house materials development and its characterization in terms of creep, low cycle fatigue and creep-fatigue properties important to design of reactor components for core, out-of-core and steam generator applications are described in the paper. Future directions for materials research and development activities involving critical issues like radiation damage resistance along with improved mechanical properties for advanced clad and wrapper materials necessary for achieving high fuel burnup and design life up to 60 years for out-of-core structural components leading to economical nuclear energy have been highlighted.
机译:先进材料的开发以及改善的高温机械性能(特别是蠕变和疲劳)非常重要,并且对于成功开发强大,安全和经济的钠冷快堆(SFR)技术起着重要作用。 SFR的组件可在苛刻的高温,复杂蠕变,疲劳和蠕变疲劳载荷条件下运行。根据不同环境,温度和负载条件下的服务要求,为不同的组件选择不同的材料。反应堆堆芯的包覆管和包裹管均选用Ti改性的15Cr-15Ni奥氏体不锈钢,它们的快中子通量高达10 15 ncm −2 s −1 以及高温。 316L(N)SS型用于核心和内部容器以及钠管线等堆芯外结构组件。对于蒸汽发生器,在所有组件中均选择了改性的9Cr-1Mo钢,液态钠和蒸汽/水共存。内部材料开发及其蠕变,低周疲劳和蠕变疲劳特性方面的一些重要经验和令人振奋的成就,对于堆芯,堆芯和蒸汽发生器反应堆组件的设计很重要本文介绍了应用程序。材料研究和开发活动的未来方向涉及关键问题,例如抗辐射破坏性以及改进的先进复合材料和包装材料的机械性能,这些是实现高燃耗和对核心部件的设计寿命长达60年所必需的,从而可带来经济效益核能已经成为重点。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

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