首页> 外国专利> PROCESS FOR SEPARATING GRAPHIC MATRIX, COATED NUCLEAR FUEL PARTICLES, AS WELL AS INSTALLATION FOR PROCESSING GRAPHIC FUEL ELEMENTS OF HIGH-TEMPERATURE NUCLEAR REACTORS FOR THE INITIAL PROCESSING STAGE OF AN INITIAL PROCESSING STAGE

PROCESS FOR SEPARATING GRAPHIC MATRIX, COATED NUCLEAR FUEL PARTICLES, AS WELL AS INSTALLATION FOR PROCESSING GRAPHIC FUEL ELEMENTS OF HIGH-TEMPERATURE NUCLEAR REACTORS FOR THE INITIAL PROCESSING STAGE OF AN INITIAL PROCESSING STAGE

机译:分离图形矩阵,包衣的核燃料颗粒的过程,以及安装用于初始处理阶段的初始处理阶段的高温核反应器的图形燃料元素的安装程序

摘要

A treating process is provided for the separation of coated nuclear fuel particles from a graphitic matrix in which the nuclear fuel particles are embedded, and an installation provides for the conditioning of graphitic fuel elements of high-temperature nuclear reactors. The graphite which encompasses the nuclear fuel particles is conducted away through the action of a brush which isolates the nuclear fuel particles together with their coatings or the nuclear particles themselves. The nuclear fuel particles which are contained in the brushed product are then separated from the comminuted graphite.
机译:提供了一种处理方法,用于从包埋有核燃料颗粒的石墨基质中分离涂覆的核燃料颗粒,并且提供了一种装置,用于调节高温核反应堆的石墨燃料元件。通过刷子的作用将包围核燃料颗粒的石墨带走,该刷子将核燃料颗粒及其涂层或核颗粒本身隔离开。然后将磨砂产品中所含的核燃料颗粒从粉碎的石墨中分离出来。

著录项

  • 公开/公告号FR2499295B1

    专利类型

  • 公开/公告日1985-10-25

    原文格式PDF

  • 申请/专利权人 KERNFORSCHUNGSANLAGE JULICH GMBH;

    申请/专利号FR19820001554

  • 发明设计人

    申请日1982-02-01

  • 分类号G21C19/00;

  • 国家 FR

  • 入库时间 2022-08-22 07:56:10

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