• Title of article

    Characteristic results and prospects of the 13Cr–1W–0.3Ti–0.3Y2O3 ODS steel

  • Author/Authors

    Eiselt، نويسنده , , Ch.Ch. and Klimenkov، نويسنده , , M. and Lindau، نويسنده , , R. and Mِslang، نويسنده , , A.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2009
  • Pages
    4
  • From page
    525
  • To page
    528
  • Abstract
    For specific blanket and divertor applications in future fusion power reactors a replacement of presently considered reduced activation ferritic martensitic (RAFM) steels as structural material by suitable oxide dispersion strengthened (ODS) ferritic martensitic steels would allow a substantial increase of the operating temperature from ∼550 °C to about 650 °C. Temperatures above 700 °C in the He cooled modular divertor concept necessitates the use of ferritic (RAF) ODS steels, which are not limited by a phase transition. Therefore a 13Cr–1W–0.3Ti–0.3Y2O3 ferritic ODS steel is being developed, using an Attritor with varying milling parameters. Afterwards the mechanically alloyed powders were encapsulated, sealed and consolidated in a hot isostatic press device. In this work, the effects of several parameter variations on the microstructure of the produced ferritic ODS-alloys, analysed by optical microscopy (OM) and high resolution TEM, as well as results of conducted mechanical tests are presented.
  • Journal title
    Journal of Nuclear Materials
  • Serial Year
    2009
  • Journal title
    Journal of Nuclear Materials
  • Record number

    1366279