• Title of article

    The reprocessing of reactor core materials

  • Author/Authors

    Wang، نويسنده , , Jing and Liu، نويسنده , , Bing-xian Shao، نويسنده , , Youlin and Lu، نويسنده , , Zhenming and Liu، نويسنده , , Malin، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2014
  • Pages
    4
  • From page
    162
  • To page
    165
  • Abstract
    Generation IV high temperature gas-cooled reactors (HTGR) are preferentially fueled by spherical fuel elements, which are composed of a fuel zone of triso-coated uranium oxide (UO2) particles and a matrix graphite layer. Unqualified coated particles and spherical fuel elements unavoidablely occur during the processing of coating UO2 kernels and embedding the coated particles into the graphite matrix. So it is necessary to reprocess the UO2 in the unqualified coated particles and spherical fuel elements to maximize the use of the reactor core materials. In this work, we present several methods to: (1) separate the coated particles from the graphite matrix and, (2) expose and recover the UO2 kernels from the coated particles. The comparison of different methods shows that the thermal oxidation of graphite by a fixed bed burner and the jet grinding of the unqualified coated particles are prosing in practice for the separation of coated particles from the graphite matrix and recovering the uranium dioxide kernels, respectively. Some other methods, such as etching the SiC layer with the active fluorine species in plasma generated by the dielectric barrier discharge (DBD) under the atmosphere also show their great potential values in the reprocessing of reactor core materials, especially for the activated and contaminated fuels.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2014
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    1594380