首页> 外文会议>Proceedings of the 3rd JAERI symposium on HTGR technologies >Some Topics on Improvement in Production Technology and Fission Product Behavior of HTTR Coated Particle Fuel
【24h】

Some Topics on Improvement in Production Technology and Fission Product Behavior of HTTR Coated Particle Fuel

机译:HTTR包覆颗粒燃料生产技术及裂变产物性能改进的若干课题

获取原文
获取原文并翻译 | 示例

摘要

In collaborations of the Japan Atomic Energy Research Institute (JAERI) and the Nuclear Fuel Industries, Ltd. (NFI), various improvements have been made on the production processes of coated fuel particles and fuel compacts, in order to reduce the failure fraction of the fuel for the High Temperature Engineering Test Reactor (HTTR). Irradiation performance of the fuels recently produced by the improved technology was successfully demonstrated by the 13th OGL-1 fuel assembly irradiation, performed in an in-pile gas loop, OGL-1.rnIn the field of fission product behavior, a peculiar distribution of ~(110m)Ag was noticed in its radial profile in the graphite sleeve; the concentration of this nuclide was markedly reduced with increasing concentration of metallic impurities including ~(60)Co. This behavior may be ascribed to competitive co-sorption of Ag and the impurities for the trapping sites on the surface of open pores in the graphite material. Obtained results so far suggest that this nuclide should be retained effectively in the highly-purified graphite sleeve under the HTTR conditions.rnAs for the ZrC-coated particle fuel being developed as an advanced HTTR fuel, much better retention of Cs was observed than for SiC-coated particles in isochronal annealing experiments at temperatures between 1500 and 2300℃; while relatively poor retention of Ru was observed for ZrC-coated particles in this temperature range.
机译:在日本原子能研究所(JAERI)和核燃料工业有限公司(NFI)的合作下,已对包覆燃料颗粒和燃料压块的生产工艺进行了各种改进,以减少燃料的失败率。高温工程测试反应堆(HTTR)的燃料。通过在堆中气体回路OGL-1中进行的第13次OGL-1燃料组件辐射成功证明了最近通过改进技术生产的燃料的辐照性能。在裂变产物行为领域,〜在石墨套筒中观察到(110m)Ag的径向轮廓。随着包括〜(60)Co的金属杂质的浓度增加,该核素的浓度显着降低。这种行为可以归因于Ag和用于石墨材料中的开孔表面上的捕获位点的杂质的竞争性共吸附。迄今为止获得的结果表明,该核素应在HTTR条件下有效保留在高度纯化的石墨套筒中。对于被开发为高级HTTR燃料的ZrC包覆颗粒燃料,观察到的Cs比SiC保留更好1500〜2300℃等温退火实验中得到的涂层颗粒;而在此温度范围内,ZrC涂层颗粒的Ru保留率相对较低。

著录项

  • 来源
  • 会议地点 Oarai(JP)
  • 作者单位

    Department of Chemistry and Fuel Research Japan Atomic Energy Research Institute Toka-mura, Naka-gun, Ibaraki-ken, 319-11, Japan;

    Department of Chemistry and Fuel Research Japan Atomic Energy Research Institute Toka-mura, Naka-gun, Ibaraki-ken, 319-11, Japan;

    Department of Chemistry and Fuel Research Japan Atomic Energy Research Institute Toka-mura, Naka-gun, Ibaraki-ken, 319-11, Japan;

    Department of Chemistry and Fuel Research Japan Atomic Energy Research Institute Toka-mura, Naka-gun, Ibaraki-ken, 319-11, Japan;

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