• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>Advanced ceramic coatings and interfaces V >A Report on the Microstructure of As-Fabricated, Heat Treated and Irradiated ZrC Coated Surrogate TRISO Particles
【24h】

A Report on the Microstructure of As-Fabricated, Heat Treated and Irradiated ZrC Coated Surrogate TRISO Particles

机译：制备，热处理和辐照ZrC涂层替代TRISO颗粒的微观结构的报告

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 carbide is a candidate to either replace or supplement silicon carbide as a coating material in fuel particles for high temperature gas-cooled reactor fuels. Desirable characteristics of ZrC as a fuel coating include high melting point, adequate fission product retention capability, appropriate neutronic characteristics, resistance to fission product palladium corrosion, and reasonable thermal conductivity. However, there is not sufficient data to demonstrate the suitability of ZrC for nuclear fuel applications. The US and Japan have initiated a collaborative Study to evaluate the feasibility of using ZrC as a fuel coating material, in which microstructural, thermophysical, and thermomechanical properties of developmental ZrC coatings are being evaluated for both unirradiated and irradiated conditions. This paper presents the results of a joint endeavor to study the microstructural evolution, including the effects of C/Zr ratio, in as-fabricated and heat treated samples of nominally stoichiometric and carbon rich ZrC coated surrogate microspheres irradiated to fluence of 2 and 6 dpa at 800 and 1250℃. Grain growth was the primary irradiation effect observed in all the samples. Microstructural examination revealed greater grain growth in stoichiometric ZrC coatings predicting mechanical unsuitability of currently proposed ZrC for nuclear fuel coating applications.
机译：碳化锆可以替代或补充碳化硅作为高温气冷反应堆燃料的燃料颗粒中的涂层材料。 ZrC作为燃料涂层的理想特性包括高熔点，足够的裂变产物保持能力，适当的中子特性，对裂变产物钯腐蚀的抵抗力以及合理的导热性。但是，没有足够的数据证明ZrC在核燃料应用中的适用性。美国和日本发起了一项合作研究，以评估将ZrC用作燃料涂层材料的可行性，其中正在对未辐照和辐照条件下的ZrC涂层的微观结构，热物理和热机械性能进行评估。本文介绍了一项共同努力的结果，旨在研究名义上化学计量的和富碳的ZrC涂层替代微球的加工后和热处理样品的微结构演变，包括C / Zr比的影响，辐照量分别为2和6 dpa。在800和1250℃。晶粒长大是所有样品中观察到的主要辐射效应。微观结构检查显示，化学计量ZrC涂层中晶粒增长更大，这预示了当前提出的ZrC在核燃料涂层应用中的机械不合适。

著录项

  • 来源
  • 会议地点 Daytona Beach FL(US);Daytona Beach FL(US)
  • 作者

    Gokul Vasudevamurthy; Yutai Katoh; Jun Aihara; Shohei Ueta; Lance L. Snead; Kazuhiro Sawa;

  • 作者单位

    University of Tennessee - Knoxville, TN, USA Materials Science Technology Division, Oak Ridge National Laboratory, TN, USA;

    rnMaterials Science Technology Division, Oak Ridge National Laboratory, TN, USA;

    rnHigh Temperature Fuel Materials Group, Japan Atomic Energy Agency, Ibaraki-ken, Japan;

    rnHigh Temperature Fuel Materials Group, Japan Atomic Energy Agency, Ibaraki-ken, Japan;

    rnMaterials Science Technology Division, Oak Ridge National Laboratory, TN, USA;

    rnHigh Temperature Fuel Materials Group, Japan Atomic Energy Agency, Ibaraki-ken, Japan;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 陶瓷工业;
  • 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