...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Transactions of the American nuclear society >Fabrication of FeCrAl Coated Zr-alloy Fuel Cladding by Cold Spray Technique
【24h】

Fabrication of FeCrAl Coated Zr-alloy Fuel Cladding by Cold Spray Technique

机译：冷喷涂技术制备FeCrAl涂层锆合金燃料熔覆层

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

Zirconium-based alloys show fairly good resistance to corrosion under the operating conditions of a pressurized- or boiling-water reactor (PWR or BWR), as well as a very low absorption cross section of thermal neutrons with limited irradiation growth and creep. These attractive properties make them well suited for use as nuclear fuel cladding and structural components in conventional light water reactors (LWRs). However, the aggressive oxidation and significant heat production of Zr-based alloys in a high-temperature steam environment could significantly increase the risk of explosion caused by hydrogen gas, as seen in the Fukushima nuclear reactor accident. As a result, issues regarding the safety of nuclear plants during severe accidents and natural disasters were raised and solutions were discussed. Although various approaches to enhance safety have been suggested, replacing current Zr-based alloys for fuel cladding with advanced materials exhibiting lower oxidation rates can be a basic solution. Many advanced materials such as FeCrAl alloys; Mn+1AXn, (MAX) phases, where n = 1 to 3, M is an early transition metal, A is an A-group (mostly ⅢA and ⅣA, or groups 13 and 14) element and X is either carbon or nitrogen; Mo; and SiC are being considered as possible candidates.
机译：锆基合金在加压或沸水反应堆（PWR或BWR）的工作条件下表现出相当好的耐腐蚀性，并且热中子的吸收截面非常低，并且辐射增长和蠕变受到限制。这些诱人的性能使其非常适合用作常规轻水反应堆（LWR）中的核燃料包壳和结构组件。然而，如在福岛核反应堆事故中所看到的那样，在高温蒸汽环境中Zr基合金的剧烈氧化和大量生热会显着增加氢气引起爆炸的风险。结果，提出了有关严重事故和自然灾害期间核电厂安全的问题，并讨论了解决方案。尽管已经提出了各种提高安全性的方法，但是用表现出较低氧化速率的先进材料代替当前的Zr基合金作为燃料包壳是一种基本解决方案。许多先进的材料，例如FeCrAl合金； Mn + 1AXn，（MAX）相，其中n = 1至3，M为早期过渡金属，A为A-基团（主要为ⅢA和ⅣA，或第13和14组）元素，X为碳或氮；莫; SiC和SiC被认为是可能的候选材料。

著录项

  • 来源
    《Transactions of the American nuclear society》 |2015年第6期|284-285|共2页
  • 作者

    Dong Jun Park; Hyun Gil Kim; Jeong Yong Park; Yang Il Jung; Jung Hwan Park; Yang Hyun Koo;

  • 作者单位

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

    Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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